ML20134B304
| ML20134B304 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/23/1997 |
| 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 | |
| ML20134B306 | List: |
| References | |
| DPR-70-A-188, DPR-75-A-171 NUDOCS 9701300027 | |
| Download: ML20134B304 (10) | |
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UNITED STATES 5
NUCLEAR REGULATORY COMMISSION k.....,/
WASHINGTON, D.C. 20555-0001 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.188 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission 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 October 24, 1996, supplemented December 23, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 set forth in 10 CFR
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Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Comission'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. DPR-70 is hereby amended to read as follows:
I 9701300027 970123 PDR ADOCK 05000272 P
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4.
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.188, 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 6
,d F'. Stolz, Directo ject Directorate ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 23, 1997 i
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ATTACHMENT TO LICENSE AMENDMENT NO.188 t
FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
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INSTRUMElfrATION 3 /4. 3. 2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION
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3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instru-mentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
2 APPLICABILIH: As shown in Table 3.3-3.
ACTION:
a.
With an ESFAS instr'anentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table l
3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value, b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS j
4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated
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OPERABLE by the perfonnance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST. operations during the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The tocal interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
The provisions of Specification 4.0.4 are not applicable to MSIV closure time testing. The provisions of Specification 4.0.4 are not applicable to the turbine driven auxiliary feedwater pump provided the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the secondary steam generator pressure is greater than 680 psig.
SALEM - UNIT 1 3/4 3-14 Amendment No.188 l
5.
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) b.
At least once per 92 days on a STAGGERED TEST BASIS by:
1.
Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1275 psig on recirculation flow.
i 2.
_ Verifying that the steam turbine-driven pump develops a i
discharge pressure of greater than or equal to 1500 psig on recirculation flow when the secondary steam generator pressure is greater than 680 psig. The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after secondary side pressure is greater than 680 psig.
c.
At least once per 18 months by:
1.
Verifying that each auxiliary feedwater automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
i 2.
Verifying that each auxiliary feedwater pump starts automatically on an actual er simulated actuation signal.
The provisions of Specification 4.0.4 are not applicable to the f
turbine driven auxiliary feedwater pump provided the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the secondary steam generator pressure is greater than 680 psig.
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J SALEM - UNIT 1 3/4 7-6 Amendment No. 188
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055H001
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- l EMBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY i
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DELMARVA POE R AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.171 j
License No. DPR-75 1.
The Nuclear Regulatory Comission (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 j
Company and Atlantic City Electric Company (the licensees) dated October 24, 1996, supplemented December 23, 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 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 Commission; C.
There is reasonable assurance: (i) that the activities authorized by 4
this amendment can be conducted without endangering the health and j
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; 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
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. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.171, 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 c-t n
. Stolz, Director oject Directorate I-Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 23, 1997 4
s ATTACMENT TO LICENSE AMENDMENT NO.171 FACILITY OPERATING LICENSE NO. DPR-75 j
DOCKET NO. 50-311 Revise Appendix A as follows:
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3/4 3-14 3/4 3-14 3/4 7-6 3/4 7-6 2
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INSTRUMElfrATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY As shown in Table 3.3-3.
ACTION:
a.
With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value, b.
With an ESFAS instrumentation channel inoperable, take the ACTION l
shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4
4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the perfonnance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific I
ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
The provisions of Specification 4.0.4 are not applicable to MSIV closure time testing. The provisions of Specification 4.0.4 are not applicable to the turbine driven auxiliary feedwater pump provided the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the secondary steam generator pressure is greater than 680 psig.
SALEM - UNIT 2 3/4 3-14 Amendment No. 171 l
c PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 92 days on a STAGGERED TEST BASIS by:
~1.
Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1275 psig on recirculation flow.
2.
Verifying that the steam turbine-driven pump develops a discharge pressure of greater than or equal to 1500 psig on recirculation flow when the secondary steam generator supply pressure is greater than 680 psig. The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after secondary side pressure is greater than 680 psig.
c.
At least once per 18 months by:
l 1.
Verifying that each auxiliary feedwater automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
i 4
2.
Verifying that each auxiliary feedwater pump starts automatically on an actual or simulated actuation signal.
The provisions of Specification 4.0.4 are not applicable to the turbine driven auxiliary feedwater pump, provided the surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the secondary steam generator pressure is greater than 680 psig.
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e SALEM - UNIT 2 3/4 7-6 Amendment No.171
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