ML20128H988
| ML20128H988 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/01/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128H992 | List: |
| References | |
| NUDOCS 8507100338 | |
| Download: ML20128H988 (8) | |
Text
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o, UNITED STATES j
NUCLEAR REGULATORY COMMISSION r E WASHINGTON. D. C. 20555 Da 1
%,..... f GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER A LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Arendment No. 87 License No. DPR-16 1.
The Nuclear RegulItory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated March 21, 1985, complies with the standards and require-m ments of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations 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 is 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 activities will be conducted in compliance with the Comission's regulations; D.
The issuance 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 apolicable requirenents have been satisfied.
8507100338 850701 PDR ADOCK 05000219 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license anendment and Paragraph F.Cl?) of Provisional Operating License No. DPR-16 is hereby amended to read as *ollevs:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.87, 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 the date of its issuance.
FOR THHiUC)$
EAR REGULAT C
- ISSION S
John
. Zwolinski, Chief Opera ing Reactors Branch #5 Division of Licensing Attechnent:
Changes to the Technical Specifications Date of Issuance: July 1, 1985
O ATTACHMENT TO LICENSE AMENDt!ENT NC.87 PROVISIONAL OPERATING LICENSE NO. DPR-16 00CF.ET FO. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed paces. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REtTVE INSERT 3.5-2 3.5-2 3.5-3 3.5-3 3.5-3a 3.5-3a 3.5-7 3.5-7 3.5-14 4.5-6a 4.5-6a t
L
3.5-2 4.
Reactor Building to Suppression Chamber Vacuum Breaker System a.
Except as specified in Specification 3.5.A.4.b below, two reactor building to suppression chamber vacuum breakers in each line shall be operable at all times when primary containment integrity is required. The set point of the differential pressure instrumentation which actuates the air-operated vacuum breakers shall not exceed 0.5 psid.
The vacuum breakers shall move from closed to fully open when subjected to a force equivalent of not greater than 0.5 psid acting on the vacuum breaker disc.
b.
From the time that one of the reactor building to suppression chamber vacuum breakers is made or found to be inoperable,,the vacuum breaker shall be locked closed and reactor operation is permissible only during the succeeding seven days unless such vacuum breaker is made operable sooner,.provided that the procedure does not violate primary containment integrity.
c.
If the limits of Specification 3.5.A.4.a are exceeded, l
reactor shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
Pressure Suppression Chamber - Orywell Vacuum Breakers a.
When primary containment is required, all suppression chamber - drywell vacuum breakers shall be operable except during. testing and as stated in Specification 3.5.A.S.b and l
c, below. Suppression chamber - drywell vacuum breakers shall be considered operable if:
(1)
The valve is demonstrated to open from closed to fully open with the applied force at all valve positions not exceeding that equivalent to 0.5 psi acting on the suppression chamoer face of the valve disk.
(2)
The valve disk will close by gravity to within not greater than 0.10 inch of any point on the seal surface of the disk when released after bein.g opened by remote or manual means.
i (3)
The position alarm system will annunciate in the I
control room if the valve is open more than 0.10 inch at any point along the seal surface of the disk.
AmendmentNo.g,g,87 l
3.5-3 b.
Two of the fourteen suppression chamber - drywell vacuum breakers may be inoperable provided that they are secured in the closed position.
c.
One position alarm circuit for each operable vacuum breaker may be inoperable for up to 15 days provided that each operable suppression chamber - drywell vacuum breaker with one defective alarm circuit is physically verified to be closed immediately and daily during this period.
6.
After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than 4.0% 0 with nitrogen gas within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor mode 7
selector switch Ts placed in the run mode. Primary contairinent deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.
7.
If specifications 3.5. A.l.a. b, c(1) and 3.5. A.2 through 3.5. A.5 cannot be met, reactor shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
8.
Shock Suppressors (Snubbers) a.
During all modes of operation except cold shutdown and refuel, all safety related snubbers listed in Table 3.5.1 shall be operable except as noted 3.5. A.8.b, c and d below.
b.
From and after the time that a snubber is detertnined to be inoperable, continued reactor operation is permissible only during the succeeding
{,
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is sooner made operable or replaced.
c.
If the requirements of 3.5. A.8.a and 3.5. A.8.b cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
d.
If a snubber is determined to be inoperable while the reactor is in the shutdown or refuel mode, the snubber shall be made operable or replaced prior to reactor startup.
e.
Snubbers may be added to safety related systems without prior License Amendment to Table 3.5.1 provided that a revision to Table 3.5.1 is included with the next License Amendment request.
P Amendment No. [, g, 87
3.5-3a B.
Secondary containment integrity shall be maintained at all times unless all of the following conditions are met:
a) The reactor is subcritical and Specification 3.2.A is met.
b) The reactor is in the cold shutdown condition.
c) The reactor vessel head or the drywell head are in place.
d) No work is being performed on the reactor or its connected systems in the reactor building which could result in inadvertent releases of radioactive material.
e) No operations are being performed in, above, or around the spent fuel storage pool that could cause release of radioactive materials.
1.1 Upon the accidental loss of secondary containnent integrity, restore secondary containment integrity within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or:
a) During Power Operation:
- 1) Have the reactor mode switch in the shutdown mode position within the following 24 nours.
- 2) Cease all work on the reactor or its connected systems in the reactor building which could result in inadvertent releases of radioactive materials.
- 3) Cease all operations in, above or around the Spent Fuel Storage Pool that could cause release of radioactive materials.
b) During refueling:
1)
Cease fuel handling operations or activities which could Amendment No. [ J,87 d
j 4
3.5-7 When secondary containment is not maintained, the additional restrictions on operation and maintenance give assurance that the probability of inadvertent releases of radioactive material will be minimized. Maintenance will not be perfomed on systems which connect to the reactor vessel lower than the top of the active fuel unless the system is isolated by at least one locked closed isolation valve.
The standby gas treatment system (6) filters and exhausts the reactor building atmosphere to the stack during secondary l
containment isolation conditions, with a minimum release of radioactive materials from the reactor building to the environs.
Two separate filter trains are provided each having 100%
capacity. (U)
If one filter train becomes inoperable, there is no imediate threat to secondary containment and reactn operation may continue while repairs are being made. Since the test interval for this system is one month (Specification 4.5),
l the time out-of-service allowance of 7 days is based on considerations presented in the Bases in Specification 3.2 for a o
one-out-of-two system.
References:
(1) FDSAR, Volume I, Section V-1
- 2) FOSAR, Volume I, Section V-1.4.1 3
FDSAR, Volume I, Section V-1.7 4
Licensing Application, Amendment 11. Question III-25 FDSAR, Volume I, Section V-2 FDSAR, Volume I, Section V-2.4 Licensing Application, Amendment 42 (8) Licensing Application, Amendment 32, Question 3 (9) Robbins, C. H., " Tests on a Full Scale 1/48 Segment of the Humboldt Bay Pressure Suppression Contaiment "
GEAP-3596, November 17, 1960.
(10) Bodega Bay Preliminary Hazards Sumary Report, Appendix I, Docket 50-205, December 28, 1962.
(11) Report H. R. Erickson, Bergen-Paterson to K. R. Goller.
NRC, October 7, 1974
Subject:
Hydraulic Shock Sway Arrestors.
(12) General Electric NEDO-22155 " Generation and Mitigation of Combustible Gas Mixtures in Inerted 8WR Mark I Containments" June 1982.
(13) Oyster Creek Nuclear Generating Station, ark I Centainment Long-Term Program, Plant Uni:ue Analysis Recort, Suppression Chamser and vent System, MPR-733; August, 1982.
(14) Oyster Creek Nuclear Generating Statien, Mark :
Centainment Long-Term Program, Plant Unicue Analysis Report, Torus Attachec Piping, MPR-73*;
% g.:s t, 1932.
j Amerdment No.k. k, JHi, 87
- 4. 5-6a P.
Suppression Chamber Surveillance 1.
At least once per day the suppression chamber water level and taperature and pressure suppression system pressure shall be checked.
2.
A visual inspection of the suppression chamber interior, including water line regions, shall be made at each major refueling outage.
3.
Whenever heat from relief valve operation is being added to the suppression pool, the pool taperature shall be continually monitored and also observed until the heat addition is terminated.
4.
Whenever operation of a relief valve is indicated and the suppression pool taperature reaches 160'F or above while the reactor primary coolant system pressure is greater than 180 psig, an external visual examination of the suppression chamber shall be made before resuming normal power operation.
Q.
Shock Suppressors (Snubbers) 1.
All hydraulic snubbers listed in Table 3.5.1 whose seal material has been dmonstrated by operating experience, lab testing or analysis to be compatible with the operating environment shall be visually inspected. This inspection shall include, but not necessarily be limited to, inspection of hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify snubber operability in accordance with the following schedule:
Number of Snubbers Found Next Required Inoperable During Inspection Inspection or During inspection interval Interval l
0 18 months + 25; l
1 12 months 7 25%
i 2
6 months 7 25%
3, 4 124 days 7 25%
i l
5,6,7 62 days 7 255 18 31 days 7 255 l
i The required inspection interval shall not be lengthened more than one step at a time.
Snubbers may be categorized in two groups, " Accessible" or " Inaccessible" based on their accessibility for inspection during reactor operation.
These two groups may be inspected independently according to the above schedule.
AmendmentNo.)d.)LI,87
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