Docket 50-320 Hr. John J. Barton Acting Director, THI-2 GPU Nuclear Corporation P.O. Sox 480 Middletown, PA 17057 Dear Hr. Barton: DISTRIBUTION: .,..- Docket so-32o NRC PDR Local PDR TERA TMIPO HQ r/f TMI Stte r/f Ularrett RBellamy Afasano RConte Attorney, ELD IE ACRS BSnyder RWeller SUbject: Recovery Operations Plan Change No. 12 (Reactor Coolant Systea Chemistry Specifications Change) Reference : Letter from J. Barton to B. Snyder, same subject, dated April 15, 1982, 4400-82-L-0054 W e have reviewed the referenced letter which transmits your Recovery Plan Change Request Humber 14 for reactor coolant systea (RCS) chemistry specifications. This change request deletes the dissolved oxygen and dissolved hy drogen specifications, and establishes a RCS chloride specification of 5 ppm 1n the Recovery Operations Plan (ROP). The staff's evaluation of these changes, wtth the supporting information on RCS sulphur analysts and the metallurgical analysts on materials used tn the submerged dem1neral1zer system, has concluded that no significant increase tn RCS system corrosion should occur, nor loss of system integrity. We therefore, approve your change request and are enclosing the sections (ROP Change Ho. 12) to the Plan. Thts ROP change is required both for the timely processing of the reactor coolant system water through the submerged demineralizer systea and the partial RCS drain down for the remote visual reactor examination through a control rod drive mechanism. We understand your staff is taking precautionary steps (i.e., prior flushing of SDS and reactor coolant bleed tanks) to insure that present RCS chloride concentration (approxiMately 0.8 ppm Cl) is not intentionally raised to the 5 ppn and that processed makeup water (returned to the RCS via RCBT •A•) will be 1nerted with nitrogen to insure dissolved oxygen is as low as practicable during processing. These are beneficial precautionary steps. Additionally. we suggest a contingency plan be considered to remove chlorides from the RCS or makeup water in the remote case where significant chlorides might leach from previously contaminated system components. . .. . .. .. . ...... ,. . . . . .... . .. . .... . . . . . ....... ... .. ... . .. .. .. . .... . .. ....... . .......... .. .. .. . .. .. .. .. .. .... ... .... .. .. . ....... . OAU . • • • .. • "'. • • • • • .. • • • • • •• • • •• •• •• ••• • • •• • • •••• • •• ••• ••• •• t • • •••• • • • •••• •• • • • •• ••• ••• t . .. . . ...... ...... . . .. ... ..... . ... . . . . .. .. . ... . ,..;.c.;o;..-o --·--·- · E R py ·-
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DISTRIBUTION: so-32o .,..- Docket NRC PDR TERA …1982-05...P.O. lox aa Hfddlttown, PA 17057-0311 Robert L. Knupp, Esquire Assistant Soltct~r Knupp and Andrtws P.O. lox P 407 H. F~nt
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Docket 50-320
Hr. John J. Barton Acting Director, THI-2 GPU Nuclear Corporation P.O. Sox 480 Middletown, PA 17057
Reference: Letter from J. Barton to B. Snyder, same subject, dated April 15, 1982, 4400-82-L-0054
We have reviewed the referenced letter which transmits your Recovery Oper~ttons Plan Change Request Humber 14 for reactor coolant systea (RCS) chemistry specifications. This change request deletes the dissolved oxygen and dissolved hydrogen specifications, and establishes a RCS chloride specification of 5 ppm 1n the Recovery Operations Plan (ROP).
The staff's evaluation of these changes, wtth the supporting information on RCS sulphur analysts and the metallurgical analysts on materials used tn the submerged dem1neral1zer system, has concluded that no significant increase tn RCS system corrosion should occur, nor loss of system integrity. We therefore, approve your change request and are enclosing the A~ended sections (ROP Change Ho. 12) to the Plan.
Thts ROP change is required both for the timely processing of the reactor coolant system water through the submerged demineralizer systea and the partial RCS drain down for the remote visual reactor examination through a control rod drive mechanism. We understand your staff is taking precautionary steps (i.e., prior flushing of SDS and reactor coolant bleed tanks) to insure that present RCS chloride concentration (approxiMately 0.8 ppm Cl) is not intentionally raised to the 5 ppn ~xi~ 11~it and that processed makeup water (returned to the RCS via RCBT •A•) will be 1nerted with nitrogen to insure dissolved oxygen is as low as practicable during processing. These are beneficial precautionary steps. Additionally. we suggest a contingency plan be considered to remove chlorides from the RCS or makeup water in the remote case where significant chlorides might leach from previously contaminated system components.
N"Ac-r"O"'il ~,~ l,aciO:wol ,..;.c.;o;..-o--·--·- · E R py ·-
Hr. John J. Barton -2-
The deletion of the RCS dissolved hydrogen (for~erly maintained above 5 ce/Kg) as an oxygen scavenger is consistent with the dissolved OxYgen change. Currently the RCS dissolved H2 1s 9 cc/Kg. While the staff is approving deletion of the dissolved H. from the ROP, prior to actual RCS depressurization/reactor ve~sel opening, the RCS dissolved ~2 should, by procedure, be lowered to less then 5 cc/Kg to insure no comoust1blc gas ~:~btures fo1""1D.
Enclosures: Page No. 4.4-1 and B 3/4 4-1
cc: See Service Oistr1but1on List
take H. Barrett Deputy Prog~ Director TMI Program Office
4.4.1 Verify that surveillance of the Reactor Coolant System ia being performed in accordance with procedures approved pursuant to Technical Specification 6.8.2.
SAFETY VALVES
4.4.3 Not applicable.
4.4.9 PRESSURF./T~~ERATURE LIMITS
r~C!OR COOLANT SYSTEM
4.4.9.1.1 The Reactor Coolant Sytem pressure and te=perature shall be determined to be within the limits at least once per 12 hours.
4.4.9.1.2 Deleted.
.. 4.4.9.1.4 The pH of the reactor coolant shall be determined tc be greater than or equal to 7.5 at least once per 7 _days.
4.4.9 . 1.4 The Chloride concentration in the reactor coolant shall ~e I ' determined to be less than or equal to 5 ppm at least once per 7 days.
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820519 C>371
THREE MILE ISLAHO - U~ I T 2 4.4-1 Change No. 12
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.. 3/~.· REACTOR COOL~NT SYSTEM
BAS!S
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3/4 ••• 1 RtiCTOR· COOLANT LOOPS
Several alternative ~ethods are available for re~oval of reactor ~c~ heat. These ~ethods include use of the ·Hini Decay Heat ~emova: Systea. the NLoss to Ambient" cooling ~ode, and operation of the Reactor Coolant S1stea fn the natural c~rculation ~ode . with heat rejection vfa the long term •a~ steaa generator cooling ~ode. Any ~ne of thele cooling methods provides adequate cooling of the reactor and each ~ethod is available for decay heat reeoval. Procedures have been prepared and approved for use of these various cooling
· methods.
· 3/4 . 4.3 SAFETY VAlVES .·
The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety li~it of 2750 psig. Each safety valve .11 designed to relieve 348,072 lbs per hour of saturated steam ~t the valve's setPoint.
3/4 ••• 9 PRESSURE/TEMPERATURE. LJHJT .
The RCS pres.sure and temperature wi1 1 be controlled in acc·ordance vith approved procedures to prevent a nonductile failure of the RCS whili at the same time permitting the RCS pressure to be m~intained at a su!ficfently high value to pe~it oper•tion of the reactor coolant pumps.
Reactor coolant chemistr,y surveillance requirements are included in the Recover.y Operati~ns Plan. These requirements provide as~urance that localized ' co: rosion or pitting in crevice areas, which could tend ~o promote stress corroiion cracking in heat affected zones of welds fn stainless steel piping or comDonents. will not occur.
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-. ~- ·--- ROPC 112
• L. (In~. Acting Mlnaver Site O~tr&!1ons TKI·2
PU N~cltar Corporation .0. loa 410 tddlttown, PA 17057
r. J.t. Larson, Supervisor I Unit 2 Lfctnsi.ng
PU Nuclear Corporation .o. loa 480 tdd\ttown, PA 17057
r. J. l . UbtrNn, Esquire erhck, hruh, Libtl'llln 6 lroadway •~ York, NY 10004
r. G.,. Trowbridge, tsquira ha~, Pitt.an, Potts l Trowbridge 800 M Street, M.W. ashingtcn, DC 20036
• Walter H. Jordan 11 w. ~ttr Drht k Rfdgt, TN 37830
• Linda w. Little 000 Hermitage Drive ltigh, Ht 27612
rin W. Carter ststant Attorney General
OS taecut1vt Houst .o. loa 2357 arrhburg, PA 17120
onorable Kark Cohen 12 £·3 Katn CApital luUd1ng arrisburg, PA 17120
Holly s. ltct Antf-Nucltar Group Representing York 245 11. Philadelphia Street York, PA 17404
John Levin Esqufrt Pennsylvania Public Ut1\1tits Conlfssioa P.O. lox 3255
. Harrhburg, PA 17120
~rdan D. Cunningha•, tsqufre Fox, ,arr and Cunninghu 2320 ~. Second Strttt Harrhburg, PA 17lt0
Ivan 11. S.fth. Esqu~t Atoaic Safety and Licensing Joard u.s. Nuclear Regule~r.r Coasissfon Washington, « 20555 . Ato~tc Safety and Licensing loard Pantl u.s. Nuclear Rtgula~ry ~1ssfon Washington, DC 20555
Atoaic Safety and Ucensfng ~ptal Pantl u.s. Nuclear Regulator¥ to.atssfon
·washington, DC 20555
Vfrgtn1a Southard, Chafnaan Cft~zens for a Saft Env1ro~nt 264 Walton Street Lnoynt, PA 17043
John F. Wolf, Esq., Cbahut\ Adatnfstrativt Judgt
3~0t Shepherd Street · Chevy Chase, HD 20015
Dr. Oscar H. Parfs, ~ln1stratfvt ~dfl . .
Ato111fc Safety and Lfctnsfng loard Pantl u.s . Nuclear Regulatory to..lssion Wuhfngton, DC 20555
Kr. Fredtrfc\ J. Shon, Adainlst ratfve Judgt
Atomi c Safety and Licensing loard. Pant\ U.S. Nuclear Rtgul atory Co~issfon ~a~hington, DC 20555