ML20100Q633
| ML20100Q633 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/09/1992 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100Q635 | List: |
| References | |
| NUDOCS 9203180290 | |
| Download: ML20100Q633 (5) | |
Text
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pn Mc%'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION g,
- E WASHINGTON, D. C. 20555
%, f PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has.found that:
A.
The application for amendment filed by the Public Service Electric
& Gas Company (PSE&G) dated Novemoer 29, 1991, and supplemented on January 31, 1992, complies with the standards and requirements 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 Commission's regulations set forth in 10 CFR Chapter I; 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 l
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.
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. NPF-57 is hereby amended to read as follows:
9203180290 920309 ADOCK0500g4 PDR P
, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 48, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE&G shall operate the facility in accordance with the. Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hgk fd Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the_ Technical Specifications Date of' Issuance:
March 9,-1992 se
ATTACHMENT'TO LICENSE AMEN 0 MENT NO. 48,
FACIllTY OPERATING LICENSE N0. NPF-57 DOCKET NO. 50-354 ReplacethefollowingpagesoftheAppendix"A"TechnicalSpecificationswith the attached-pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4
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CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) b.
The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *, valves which form the boundary for the long-term seal of the feedwater lines, and other valves which are hydrostatically tested per Table 3.fr.3-1, subject to Type B eno C tests to less than or equal to 0.60 L, and a
The leakage rate to less than or equal to 46.0 scfh combined through c.
all four main-team lines, and d.
The corbined leakage rate for all containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 to less than or equal to 10 gpm, and e.
The combined leakage rate for all other penetrations and containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment to less than or equal.,t.o 10 gpm,.
prior to increasihg reactor coolant system temperature above 200 F.
SURVEILLANCE REQUIREMENTS.
4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
Three Type A Overall Inte0 rated Containment Leakage Rate tests shall a.
be conducted at 40 + 10 month intervals *" during shutdown at P '
a 48.1 psig, during each 10 yect service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection, b.
If any periodic Type A test fails to meet 0.75 L,, the test schedule for subsequent Type A tests shall be. reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L, a 3
Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L,, at which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is witnin 0.25 L
- a
- Exemption to Appendix "J" of 10 CFR 50.
- The maximum permissible test interval for the second Type A test of the first ten year service period is extended to 56 months.
This extension expires upon completion of the second Type A test of the fdrst tan year service period.
HOPE CREEK 3/4 6-3 Amendment No. 48
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4 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
Has duration sufficient to establish accurately the-change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the contai gent or bled from the containment during the supplemental test to be between 0.75 l and 1.25 L,.
a The formula to be used is:
[L
+ L
- 0.25 L,] $ Lc 5 [L
+ L g
am g
am 0.25-L ) where L s supplement test result; L a superimposed leakage; a
c g
and L, a measured Type A leakage.
d.
Type B and C tests shall be conducted with gas at P ' 40'1 PSI *'
9 a
at intervals no s.,cter than 24 months except for tests invol,ving:
1.
Air locks, 2.
Main steam line isoletion valves, 3.
Valves pressurized with fluid from a seal system, 4.
All containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment, and 5.
Purge supply and exhaust isolation valves with resilient material seals.
e.
Air locks shall be tested ar.d demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once per 18 months.
g.
Containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 shall be hydrostati-cally tested at 1.10 P, 52.9 psig, at least once per 18 months.
a h.
All containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment shall be leak-tested at least once per 18 months, i.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4.6.1.8.2.
j.
The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.c, 4.6.1.2.d, and 4.6.1.2.e.
"Unless a hydrostatic test is required per Table 3.6.3-1.
HOPE CREEK 3/4 6-4 Amendment No. 48