ML20097J623
| ML20097J623 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/25/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20097J628 | List: |
| References | |
| NPF-39-A-108, NPF-85-A-071 NUDOCS 9602050063 | |
| Download: ML20097J623 (5) | |
Text
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ecified limit and the leakage area for an individual set of vacuum brea(ers is less than or equal to 12% of the specified limit. The vacuum breaker leakage test shall be conducted during each refueling outage for which the drywell-to-suppression chamber bypass leak test in Specification 4.6.2.1.e is not conducted. l
- The CHANNEL CALIBRATION for level transmitters LT-55-1N0628, -lN062F shall be performed at least once per 18 months.
LIMERICK - UNIT 1 3/4 6-14 Anendment No. SS, 70, 7I,108 1 a 40o
- 1 UNITED STATES
.p NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 20066 4 001 '+,*****,o i PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.71 License No. NPF-85 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Philadelphia Electric Company (the licensee) dated June 20, 1995, 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 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 l E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical l Specifications as indicated in the attachment to this license amendment, l and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows: Technical Soecifications l The Technical Specifications contained in Appendix A and the Environmental l Protection Plan contained in Appendix B, as revised through Amendment No. 71, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days. FOR THE NUCLEAR REGULATORY COMMISSION J olz, Direct P o ect Directorate I-2 ' ision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 25, 1996 i
)
ATTACHMENT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 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 indicatir.g the areas of change.
RehtoVe Insert 3/4 6-3
.3/4 6-3 3/4 6-14 3/4 6-14 e
CONTAINMENT SYSTEMS
~
LIMITING CONDITION FOR OPERATION (Continued) l ACTION:
(Continued) b.
The combined leakage rate for all penetrations and all valves listed I
in Table 3.6.3-1, except for main steam line isolation valves
- and valves which are hydrostatically tested per Table 3.6.3-1, subject to Typ B and C tests to less than or equal to 0.60 La, and c.
The leakage rate to s11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage to $200 scf per hour, and d.
The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to increasing reactor coolant system temperature above 200*F.
SURVEILLANCE REOUIREMENTS 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 Part 50 using the methods and provisions of ANSI 45.4-1972 and BN-TOP-1 and verifying the result by the Mass Point Methodology described in ANSI N56.8-1981:
a.
Type A Overall Integrated Containment Leakage Rate tests shall be conducted at Pa, in accordance with 10CFR50, Appendix J, as modified by approved exemptions, b.
If any periodic Type A test fails, or if two consecutive Type A tests fail, a Type A test shall be performed in accordance with 10CFR50, Appendix J, as modified by approved exemptions, 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 within 0.25 La. The formula to be used is: (Lo + Lam -0.25 La] 5 Lc s [Lo + Lam + 0.25 La] where Lc - supplemental test result; Lo -
superimposed leakage; Lam - measured Type A leakage.
2.
Has durat 9n sufficient to establish act.urately the cnange in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be between 0.75 La and 1.25 La-
- Exemption to Appendix "J" to 10 CFR Part 50.
LIMERICK - UNIT'2 3/4 6-3 Amendment No. 53, 71
1 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
By verifying at least 8 suppression pool water temperature indicators in at least 8 locations, OPERABLE by performance of a:
1.
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.
CHANNEL CALIBRATION at least once per 24 months, with the temperature alar,setpoint for:
1.
High water temperature:
a)
First setpoint s 95'F b)
Second setpoint s 105'F c)
Third setpoint s 110*F d)
Fourth setpoint s 120'F d.
By verifying at least two suppression chamber water level indicators OPERABLE by performance of a:
1.
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.
CHANNEL FUNCTIONAL TEST at least once per 92 days, and 3.
CHANNEL CALIBRATION at least once per 24* months, with the water level alarm setpoint for high water leml s 24'l-1/2" e.
Drywell-to-suppression chamber bypass leak tests shall be conducted to coincide with the Type A test (in accordance with 10CFR50, Appendix J, as modified by approved exemptions) at an initial differential pressure of 4 psi and ' verifying that the Alk caluculation from the measured leakage is within the specified limit.
If any drywell-to-suppression chamber bypass leak test fails to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission.
If two consecutive tests fail to meet the specified limit, a test shall be performed at least every 24 months until two consecutive tests meet the specified limit, at which time the test schedule may be resumed.
f.
By conducting a leakage test on the drywell-to-suppression chamber vacuum breakers at a differential pressure of at least 4.0 psi and verifying that the total leakage area A/(k contributed by all vacuum breakers is less than or equal to 24% of the specified limit and the leakage area for an individual set of vacuum breakers is less than or equal to 12% of the specified limit. The vacuum breaker leakage test shall be conducted during each refueling outage for which the drywell-to-suppression chamber bypass leak test in Specification 4.6.2.1.e is not conducted.
l
"" The cRANNEL CALIBRATION for level transmittcrs LT-55-2N0628, -2N062F shall be performed at least once per 18 months.
LIMERICK - UNIT 2 3/4 6-14 Amendment No. 31, 33, 34, 71