ML20082L306

Rev 1 to Application to Amend License DPR-50,consisting of Tech Spec Change Request 116,revising Purge Valve Operating Limits

ML20082L306
Person / Time
Site:	Three Mile Island
Issue date:	11/24/1983
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20082L280	List: ML20082L277 ML20082L306 ML20082L323
References
NUDOCS 8312050466
Download: ML20082L306 (7)

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METROPOLITAN EDISON COM ANY JERSEY CENTRAL POWER & LIGHT COM:ANY AND PENNSYLVANIA ELECTRIC C0tPANY TEREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289

• Technical Specification Change Request No, 116 Revision 1 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replacement pages for Appendix A are also includea.

s ,flJCLEAR CORPORATION By Director, TM1-1 Sworn and subscribed '

to before me this 24th day of November , 1983, i

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Notfry Public OARI A JEAN B!irxY NOIAWY PUE!!C MIDD!.fiO AN E040 Cal!N!% COUNit WY CCMM4590N f APIRIS JUNI 17.1985 Member. Pennsylonia Association et Netma 8312050466 831124 PDR ADOCK 05000289 P PDR

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

IN THE MATTER OF l

DOCKET NO. 50-289 LICENSE NO. DPR-50 GPU NUCLEAR CORPORATION This is to certify that a copy of Technical Specification Change Request No, 116 Rev. 1 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U.S. Nuclear Regulatory Commission and been served on the chief executives of

• Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:

Mr. Jay H. Kopp, Chairman Mr. John E. Minnich, Chairman Board of Supervisors of Board of County Comissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 Mr. Thomas Gerusky, Director Penna. Dept. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120 a

GDU N'JCLEAR CORPORATION BY t Director, TMI-l DATED: November 24, 1983

4 TECH 9ICAL SPECIFICATION CHANGE REQUEST NO.136 REVISION 1 I. Technical Specification Chance Reouest No.116 Rev.1 The Licensee requests that attached revised pages replace the following pages of the existing Technical Specifications.

Replace: 111, 3-8, 3-9, 3-41, 3-41a, 3-62a, 3-62b, 4-Sa, 4-9, 4-10, 4-34, 4-34a, 4-34b, 4-37, 4-38, 4-55b, 4-55c, 4-60, 4-61, 4-62, 4-76, 6-17, and insert new pages: 3-9a, 3-90, 3-41b.

II. Reasons for Change The purpose of this Technical Specification Change Request is to resolve NRC safety issue B-24 for TMI-1. Detailed changes are listed below.

Page No. Specific Change Reason for Change iii DELETED 4.4.3 H2 Purge System is no longer required. TSCR #114 supersedes e H2 detector surveillances of 4.4.3.3.

3-8 Added T.S. for iodine NRC requested change to assist in.

spiking for primary resolution of NRC safety issue coolant. B-24.

3-9 Added T.S. for iodine NRC requestec change to assist in spiking for primary resolution of NRC safety issue 3-9a coolant. B-24, 3-9b Added Figure 3.1-2a. Figure required for new I-131 primary coolant activity requirement above.

3-41 Action requirements to To provide more conservative purge valves have been guidance for responding to an added and TS 3.6.6 revised inoperable purge valve and to exclude purge valves. seperate it from the guidance T.S. 3.6.7 added for for other containment boundary purge valves. valves.

3-41a Added TS 3.6.8, 3.6.9 and TS 3.6.8 was added to provide 3.6.10. guidance concerning inoperable purge valves.

TS 3.6.9 was added to limit purge valve opening during operation and hot shutdown by use of positive position limiters.

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TS 3.6.10 was added to waive the position limiting requirement when the reactor is in cold shutdown.

3-41b Basis change. The bases have been changed to reflect the new specification added.

3-62a & b TS 3.15.2 changed to T.S. 3.15.2.1 is revised to be add containment integrity applicable onl/ when the reactor considerations, and reflect building is being purged since true system design bases, when no purging is being accom-and flow rate. plished it is not needed.

T.S. 3.15.2.2c was deleted since it was a surveillance requirement and was placed in new T.S. 4.12.2.2e.

T.S. 3.15 bases are revised to delete discussions of purge under post LOCA conditions since the .

system is designed only for addressing normal releases (i.e.

purging) and fuel handling accidents in containment.

4-Sa RM-G5 is excepted from RM-G5 is exempted from quarterly quarterly calibration calibration since it is in the reactor building and to minimize entries when purging is not

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permitted (for ALARA reasons) calibration is deferred until shutdown when full purging is permitted.

4-9 & Added surveillance for Surveillances for coolant iodine 4-10 iodine spiking, have been added consistent with the changes on pages 3-8, 3-9, 3-9a, and 3-9b.

4-34 T.S. 4.4.1.2.5 changed to NRC requested change to assist reflect purge valve test in resolution of NRC safety frequency and acceptance issue B-24 criteria. Item "d" in current T.S. changed to item "e".

4-34a 1. T.S. 4.4.1.6 changed to 1. Six month checks of personnel require only refueling and emergency hatch interlocks frequency operability involve containment entries checks if purging is which may not be advisable not permitted. because cf ALARA reasons without

2. T.S. 4.4.1.7 added, a purge of containment.

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2. NRC requested change to assist in resolution of NRC safety issue B-24.

4-34b Last paragraph added to NRC requested change to assist in bases for T.S. 4.4. resolution of NRC safety issue Discussion of new T.S. B-24 4.4.1.7.

4-37 & Tech. Spec. Section 4.4.3 With the installation of a H2 4-38 deleted, including bases recombiner and provisions for a second H2 recombiner completed the need for the H2 purge system has been eliminated. H2 purge exhaust isolation valves will remain closed, since the H2 purge system is not relied upon to mitigate an accident.

e 4-55b & T.S. 4.12.2.1 and 4.12.2.2a Lower system usage should decrease.

4-55c surveillance frequency potential for filter inoperability changed to 2 years instead therefore surveillance frequency of 18 months. 72 hr. retest may be adjusted. Since H2 requirement replaced with purge is not required R.B requirement that retest be purge filters no longer perform performed within 30 days an operating accident mitigation' of refueling. function.

Existing T.S. 4.12.2.2.e. The requirement to run purge changed. Basis also changed. exhaust fans monthly is superfluous since purge fans are no longer relied upon to mitigate an accident during operation.

Surveillance from former T.S.

3.15.2c inserted as 4.12.2.2e.

Also correct title for unit superintendent inserted in basis.

T.S. 4.12.2.3 changed to Clarification of existing Tech Spec require air distribution wording.

test at full R.B. purge system flowrate.

4-60, T.S. 4.17.1 & 4.17.2 changed Without purge operation noble gas 4-61 & to alter surveillance fre- build-up in containment may pose 4-62 quency when purging is not an ALARA concern for personnel permitted. Basis also in doing surveillances at existirg changed. P. 4-62 is only frequency.

text carry-over.

4-76 Note added to T.S. Same as P. 4-60 above.

4.18.6.la&b.

6-17 Added item (6), new special Report is required per new report to T.S. 6.9.3.A. T.S. 3.1.4 Ol89R

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, III. Safety Evaluation and Justification of Change This Technical Specification Change Request is submitted in response to NRC letter dated July 8, 1983. After submittal of TSCR #116 the NRC staff both requested and provided additional information relative to the resolution of Safety Issue B-24. It became apparent, that with the new s requests of inclusion of more restrictions in the Technical Specifications, that a revision to TSCR #116 was needed.

Each of.the specific changes requested by the tRC staff have been appropriately incorporated in the new changed pages to Appendix A to the license. The NRC requested changes are incorporated in accordance with the NRC staff accepted method for the resolution of Safety Issue B-24 and as such do not:

a) involve an increase in the probability of occurrence or the consequences of an accident previously evaluated, since additional surveillance requirements have been provided to assure the operability of purge isolation valves and more restrictive Reactor Coolant Activity limits have been incorporated; e b) create the possibility of an accident or malfunction of a new or different kind of accident from any previously evaluated, since limitations on purge valve position during operation have been included, thereby ensuring containment isolation capability; or c) involve a reduction in the margin of safety, for reasons stated above which ensure that offsite doses for postulated LOCA's will be

- kept within acceptable limits and improved post accident hydrogen management is provided by changes approved by License Amendment 87.

Additionally, flexibility has been provided for surveillances in the Containment, since restrictions on purging during operation may pose an ALARA concern.

IV. No Significant Hazard Considerations Operation of TMI-l in accordance with this Tech. Spec. Change Request would not:

1) involve a significant increase in the probability or consequences of an accident previously evaluated since this change increases restrictions on reactor coolant activity and purge valve operation thereby enhancing safety;

2) create the possibility of a new or different kind of accident from any accident previously evaluated; it provides additional assurance that the plant (i.e. purge isolation)'

will respond to an accident as designed; or 0189R

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3) involve a significant reduction in a margin of safety since it increases the margin of safety by providing additional assurance that offsite doses for postulated LOCA's will be kept within acceptable limits and improved post acdident hydrogen management is provided by a hydrogen recombiner (License Amendment 87).

V. Implementation Because of the extensive nature of this change and the need to train operating personnel it is requested that the implementation of this '

amendment be six weeks after issuance.

VI. Amendment Classification (10 CFR 170.22)

This change request involves a single safety issue and is, therefore, considered a class III amendment. This is a revision to a previously submitted change (No. 116) for which a fee was paid. Therefore no additional fee is required.

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