ML20029B347
| ML20029B347 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/05/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co, Metropolitan Edison Co, Pennsylvania Electric Co |
| Shared Package | |
| ML20029B348 | List: |
| References | |
| DPR-50-A-160 NUDOCS 9103070081 | |
| Download: ML20029B347 (5) | |
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL PUWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY, GPU NU_ CLEAR CORPORATION DOCKET NO. 50-289 THRCE MllE ISLAND 'jUCLEAR STATION, UNIT NO.1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.160 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commibsien) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated September 25, 1990 complies with tlie standards and requirements of the Atomic Energy Act of 1/54, as amended (the Act), and the Commission's rules and regulstions set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There 1s reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such actfuities will be conducted in compliance with the Commission's regulations; D.
The issuarece of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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E 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No.
OPR-50 is hereby amended to read as follows:
(2) Technical Specificatio3 The Technical Specifications contained in Appendix A, as revised through Amendment No. 160, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its data ef issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$, $$0 5 John F. Stolz, Director Project Directorate 1-4 Division of Reactor Project = - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the "lechnical specificaUoiv Date of Issuance: March 5,1991
ATTACHMENT TO LICENSE AMENDMENT NO.160 FACILITY OPERATING LICENSE NO. OPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 4-34 4-34 4-34b 4-34b l
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..m 4.4.1,5 Peactor Building Modifications Any major modification or replacement of compohents affectiiig the reactor hid'fing integrity shall be followed by either an integrated leak rate ti-at or a,!ocal leak test, as appropriate, and shall meet the accer.
s criteria of 4,4.1.1.6 and 4.4.1.2.3, respectivaly.
4.4.1.6 Operability of Access Hatch Interlocks 1.
At least once Der six months the operability of the personnel and emergency haten door interlocks and the associated control room annunciator circuits shall be de: ermined.
If the interlock permits both doors to be open at the same time or does not provide accurate status indication in tnc control room the interlock shall be declared inoperable.
2.
During periods when containment integrity is required and an interlock is inoperable, each entry and exit via that airlock shall be locally supervised by a member c^ the unit operating maintenance or technical staffs, to assure that only one door is open at any time and that both doors are prcperly closed following use. A record of supervision and verification of clos"re shall be maintained during periods of interlock inept'obility in an appropriate station log.
3.
If an interlock is Inoperable for more tLan ~4 days following determination of inoperability, use of the airlock, ex: apt for emergency purposes, shall be suspended until the interlock is returned to operable status.
A.4.1.7 Operability of Purgo Valvar, 1.
A periodic pressurization i ! tha v. ige valve interspaces to 50.6 psig per Specification 4.4.'.2.5.d shall be performed to help assure timely detection and resolution 'f valve and/or actuator degradation. The acceptance criteria is that total local leakage when updated for the new purge valve leakage shall be ' ass than 0.6L. See Specification 3.6.8 for 4
further action.
2.
The rubber seats on purge valves shall be visually examined and durometer tested each refueling interval to detect degradation (e.g. cracking, britcleness, etc.) and to assure timely cicaning, lubrication, and seat replacetent.
a 4-34 Amendmein Nos. 63, 108, 113, 151, 160
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More frequent testing of various penetrations is specified as these locations are more-susceptible to leakage than the reactor building liner due to the mechanical closure involved. The basis for specifying a total leakage rate of 0.6 L from those penetrations
- and isolation valves is that more than one-half of the allowable integrated leakage rate will be from these sources.
Valve operability tests are specified to assure proper closure or opening of the reactor building isolation valves to provide for
. isolation or functioning of Engineered Safety Features systems, Valves will be stroked to the position required to fulfill their safety function unless it is establish that such asting is not practical during operation, Valves that cannot be full-sti'oke tested will be part-stroke testad during operation and full-stroke tested during each normal refueling shutdown.
Periodic surveillance of the airlock interlock systems is specified to assure continued operabilicy and preclude instances where-one or both doors are inadvertently left open. When an airlock is inoperable and containment integrity is required, local supervision of airlock oreration is specified.
purge valve interspace pressurization test operability requirements, inspections, and de ometer testing provida, a high degree of assurance of purge valve F'rformance as containment barriers, L
Re ferences (1) UFSAR, Chapter 5,7.4
" Post Opera tional Leakage Ra te Tests" (2). UFSAR, Tables 5.7-1 and 5.7-3 I.
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4-34b Amen
- Nos. 36, 63,108,113,151,15 7, 160 l
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