ML20203B513
| ML20203B513 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/29/1998 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20203B516 | List: |
| References | |
| DPR-70-A-206 NUDOCS 9802240308 | |
| Download: ML20203B513 (6) | |
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UNITED STATES a
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 30666-0001 PUBLIC SERVICE ELECTRIC h GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENER/. TING STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.206 Ucense No. DPR 70 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, Philadelphia Electric Company, Delmarva Power and Ught Company and Atlantic City Electric Company (the licensees) dated December 11,1997, 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 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 Ucense No. DPR-70 it hereby amended to read as follows:
9002240308 980129 PDR ADOCK 05000272 P
2' (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No 206 are hereby incorporated in the license. The licensee r. hall operate the facility in accordance with ine Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within seven days.
FOR THE NUCLEAR REGULATORY COMMISSION 4
f M.
John F. Stolz, Director Project Directorate 1-2 Division of Reactor Projects - t/ll Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofIssuance: Oa nuary 29, 1998
ATTACHMENT TO LICENSE AMENDMENT No. 206 fAQll'
)PERATING LICENSE NO. DPR 70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Panes insert Panes 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6 2 3/4 6-8a 3/4 6-8a n
3/4_6 CONTAINMENT SYSTEMS 3/4.6.1 PRTW19Y CONTATWWWWT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3. ti. l.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODIS 1, 2, 3 and 4. **
)
ACTIOM:
Wiihout primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOW within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that:
a.
1.
All penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be 7
closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are opened under administrative control as permitted by Specification 3.6.3.1.,
and 2.
All equipment hatches are closed and sealed.
b.
By verifying that each containment air lock is OPERABLE per specification 3.6.1.3.
- Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containment, and (3) locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed at least once per 92 days.
- A one-time change is granted to have the containment purge supply and/or exhaust isolation valves open in Modes 3 and 4 following the steam generator replacement outage (lR13). The cumulative t4== for having the valves open in Modes 3 and 4 is limited to fourteen (141 daga.
Each valve will be immobilized in the shut position prior to initial entry into Mode 2.
The one-time exemption expires with initial entry into Mode 2 following 1R13.
SALEM - UNIT 1 3/4 6-1 Amendment No. 4 49, 206
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COMTAI1GRINT SYETEMS i
1 couTAIMatINT LMaxAcaE I
LIMITING CONDITION FOR OPERATION
...........u..................................................................
t 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of $ La, 0.10 percent by weight j
of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at design pressure, (47.0 j
peig).
J 4
b.
A combined leakage rate of 5 0.60 La for all penetrations and valves subject to Type B and C tests, when pressurised to Pa.
APPLICABILITY: MODES 1, 2, 3 and 4. *
- ACTION:
Nith either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the leakage rate (s) to within the limit (s) prior to increasitsg the Reactor Coolant System temperature above 200'F.
i SURVEILLANCE REQUIREMENTS i
4.6.1.2 The containment leakage rates shall be demonstrated as follows:
s.
Type A tests shall be in accordance with 10CFR 50.54 (0) in conformance with Appendix J of 10CFR 50, Option 3, using the methods and provisions of Regulatory Guide 1.163, September 1995 as modified by approved exemptions.
1 b.
Type 3 and C tests shall be conducted in conforme.nce with Appendix J of 10CFR 50, Option A, with gas at design pressure (47.0 psig) at intervals no praater than 24 months except for tests involving air locks.
c.
Air locks shall be tested and demonstrated OPERABLE in conformance with Appendix J of 10CFR 50, Option A, per surveillance Requirement 4.6.1.3.
- A one-time change is granted to have the containment purge supply and/or exhaust isolation valves open in Modes 3 and 4 following the steam generator replacement outage (1R13). The cumulative t4== for having the valves open in Modes 3 and 4 is limited to fourtaan fidi dava.
Each valve
~
will be immobilised in the shut position prior to initial entry into Mode 2.
The one-time exemption expires with initial entry into Mode 2 following in13.
SALEM - UNIT 1 3/4 6-2 Amendment No. -M9, 2 06
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CONTAIMMENT SYSTEMS CONTAIMMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust isolation valves
- shall be closed. (Valves immobilised in shut position with control air to valve operators isolated and tagged out of service).
APPLICAEILITY: MODIS 1, 2, 3, and 4. **
E"21938 with one containment purge supply and/or exhavst isolation valve open, close the open valv2(s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.7 The containment purge supply and exhaust isolation valves shall be determined closed at least once per 31 days.
- A one time change is granted to have the containment purge supply and/or exhaust isolation valves open in Modes 3 and 4 following the steam generator replacement outage (1R13). The cumulative tima for having the valves open in Modes 3 and 4 is limited to fourteen (14) days.
Each valve will be immobilised in the shut position prior to initial entry into Mode 2.
The one-time exemption expires with initial entry into Mode 2 following 1R13.
4
- The containment pressure-vacuum relief isolation valves may be opened on an intermittent basis, uraer administrative control, as necessary to satisfy the requirement of Specification 3.6.1.4.
SALEM - UNIT 1 3/4 6-8a Amendment No. 44, 206