ML20115D351
| ML20115D351 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/11/1996 |
| 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 | |
| ML20115D359 | List: |
| References | |
| RTR-REGGD-01.163, DPR-70-A-184, DPR-75-A-166 NUDOCS 9607150126 | |
| Download: ML20115D351 (12) | |
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UNITED STATES q,) #'
E NUCLEAR REGULATORY COMMISSION 2
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WASHINGTON, D.C. 20065 4 001 g...../
i PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY l
ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.184 License 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 Light Company and Atlantic City Electric Company (the licensees) dated April 22, 1996, as supplemented June 12, 1996, 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 (FR 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 l
this amendment can be conducted without endangering the health and
. safety of the public, and (ii) that such activities will be conducted l
in compliance with the Commission's regulations set forth in 10 CFR Chapter I; l
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 i
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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby amended to read as follows:
9607150126 960711
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PDR ADOCK 05000272 P
. (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 184, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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John F. Stolz, Director h Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 11,1996
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ATTACHMENT TO LICENSE AMENDMENT N0.184 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
i Remove Paaes Insert Paaes 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3, 3/4 6-4 3/4 6-4
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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated lea Te rate of s La, 0.10 percent by weight of the containment air pe: 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 psig).
b.
A combined leakage rate of s 0.60 La for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to Pa.
APPLICABILITY:
MODES 1, 2,
3 and 4.
ACTION:
With 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 increasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated as follows:
a.
Type A tests shall be in accordance with 10CFR 50.54 (0) in conformance with Appendix J of 10CFR 50, Option B, using the mechods and provisions of Regulatory Guide 1.163, September 1995 as modified by approved exemptions.
b.
Type B and C tests shall be conducted in conformance with Appendix J of 10CFR 50, Option A, with gas at design pressure (47.0 psig) at intervals no greater 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.
l SALEM - UNIT 1 3/4 6-2 Amendment No.T84 l
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PAGES 3/4 6-3 AND 3/4 6-4 ARE INTENTIONALLY BLANK i
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1 SALEM - UNIT 1 3/4 6-3, 3/4 6-4 Amendment No.184
1 CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR C,ERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.
APPLICABILIIX: MODES 1, 2,
3 and 4.
ACTION:
With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.
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SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined by a visual inspect;on of these.urfaces.
This inspection shall be performed prior to the Type A containment leakage rate test (reference Specification 4.6.1.2) to verily no apparent changes in appearance or other abnormal degradation. If che Type A test is performed at i
10 year intervals, two additional inspections shall be performed at appr:ximately equal intervals during shutdowns between Type A tests.
4.6.1.6.2 Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be evaluated for reportability pursuant to 10CFR50.72 and 10CFR50.73.
The evaluation shall be documented and shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective action taken.
SALEM - UNIT 1 3/4 6-8 Amendment No.184
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30866 0001 l
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.... 4 PUBLIC SERVICE ELECTRIC & GA$ COMPANY j
PHILADELPHIA ELECTRIC COMPANY t
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DELMARVA POWER AND LIGHT COMPANY i
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ATLANTIC CITY ELECTRIC COMPANY j-DOCKET NO. 50-311 l
SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 l
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j AMENDMENT TO FACILITY CPERATING LICENSE i
l Amendment No.166 License No. DPR-75' l
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
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A.
TheapplihationforamendmentfiledbythePublicServiceElectric&
Gas Company, Philadelphia Electric Company, Delmarva Power and LightL j
Company and Atlantic City Electric Company (the licensees) dated April 22, 1996, as supplemented June 12,_1996,' complies with the j
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set 2
i forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
l Commission; i
C.
There is reasonable assurance: (i) that the activities authorized by l
this amendment can be conducted without endangering the health and i
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; 4
1 D.
The issuance of this amendment will not be inimical to the common I
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 Specnica-l:
tions as indicated in the attachment to this license amendment, and 1
paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby i
amended to read as follows:
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. (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.166 are hereby incorporated in the 1* cense. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION cw I L /f'~%AA^
John F. Stolz, Director ['
Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 11, 1996 l
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ATTACHMENT TO LICENSE AMENDMENT NO.166 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 t
Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-8 3/4 6-8
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I CONTAINMENT SYSTEMS L
CONTAINMENT LEAKAGE I
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LIMITING CONDITION FOR' OPERATION e
h 3.6.1.2 containment leakage rates shall be limited to:
An overall integrated leakage rate of less than or equal to La, a.
0.10 percent by weight 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 psig).
't b.
A combined leakage' rate of less than or equal to 0.60 La for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to Pa.
i APPLICABILITY:
MODES 1, 2,
3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 I a, 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 overall integrated leakage rate to less than or equal to 0.75 La 3
and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 La prior to increasing the Reactor Coolant l
System temperature above 200*F.
SURVEILLANCE REQUIREMENTS l
4.6.1.2 The containment leakage rates-shall be demonstrated as follows:
i a.
Type A tests shall be in accordance with 10CFR 50.54 (0) in
[
conformance with Appendix J of 10CFR 50, Option B, using the j
methods and provisions of Regulatory Guide 1.163, September 1995 t
as modified by approved exemptions.
I b.
Type B and C tests shall be conducted in conformance with Appendix J of 10CFR 50, Option A, with gas at design pressure (47.0 psig) at intervals no greater 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.
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SALEM - UNIT 2 3/4 6-2 Amendment No.166
PAGE 3/4 6-3 IS INTENTIONALLY BLANK
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SALEM - UNIT 2 3/4 6-3 Amendment No.166
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CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level. consistent with the acceptance criteria in Specification 4.6.1.6.
l APPLICABILITY: MODES 1, 2,
3 and 4.
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ACTION:
With the structural integrity of the containment not conforming to the above j
requirements, restore the structural integrity to within the limits within 24 l
hours 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 i
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 4.6.1.6.1 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined by'a visual inspection of these surfaces.
This inspection shall be performed prior to the Type A containment leakage rate test (reference Specification 4.6.1.2) to verify no apparent changes in appearance or other abnormal degradation.
If the Type A test is performed at 10 year intervals, two additional inspections shall be performed at approximately equal intervals during shutdowns between Type A l
tests.
l 4.6.1.6.2 Reoorts-Any abnormal degradation of the containment structure detected during the above required inspections shall be evaluated for reportability pursuant to 10CFR50.72 and 10CFR50.73.
The evaluation shall be documented and shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and'the corrective action taken.
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SALEM - UNIT 2 3/4 6-8 Amendment No. 112, 166 l
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