ML20076K894
| ML20076K894 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/20/1994 |
| 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 | |
| ML20076K897 | List: |
| References | |
| DPR-70-A-158, DPR-75-A-139 NUDOCS 9411020178 | |
| Download: ML20076K894 (10) | |
Text
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.y UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20066-4001
,o PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY
'l DELMARVA POWER AND LIGHT COMPANY
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ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-272 SAliM NUCLEAR GENERATING STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE i
i Amendment No.158 License No. DPR-70 l
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
J 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 February 18, 1994, as supplemented by letter dated April 6, 1994, 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; i
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; 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-70 is hereby l
amended to read as follows d
l 9411020178 941020 l
PDR ADOCK 05000272 P
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' (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.158, 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 and shall be implemented within 60 days of the date of issuance'.
FOR THE NUCLEAR REGULATORY' COMMISSION M [c M 1T/
John F. Stolz, Director Project Directorate I-2 i
Division of Reactor Projects
.I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: October 20, 1994 l
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1 I
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r ATTACHMENT TO LICENSE AMENDMENT N0,158 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET N0. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 6-13 3/4 6-13 3/4 6-15 3/4 6-15 3/4 6-17 3/4 6-17 3/4 6-17a t
CONTAINMENT. SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
==================================================================
4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
c.
Not Used, d.
Verifying that on a Containment Purge and Pressure-Vacuum Relie$
isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position.
e.
Verifying that the Containment rressure-Vacuum Relief Isolation valves are limited to s 60* opening angle.
4.6.3.1.3 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve specified in Table 3.6-1 actuates to its isolation position.
4.6.3.1.4 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.1.5 Each containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60La.
4.6.3.1.6 A pressure drop test to identify excessive degradation of resilient valve seals shall be conducted en the:
a.
Containment Purge Supply and Exhaust Isolation Valves at least once per 6 months.
b.
Containment Pressure - Vacuum Relief Isolation Valves at least once per 3 months.
SALEM - UNIT 1 3/4 6-13 Amendment No.158
TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES VALVE NUMBEB FUNCTION ISOLATION TIME (Seconds)
D.
NOT USED E.
STEAM GENERATOR BLOWDOWN ISOLATION 1.
11 GB 4#
Steam Generator Blowdown s10Sec.
2.
12 GB 4#
Steam Generator Blowdown s10Sec.
3.
13 GB 4#
Steam Generator Blowdown s10Sec.
4.
14 GB de Steam Generator Blowdown s10Sec.
5.
11 SS 9,#
SG Blowdown Sampling s10Sec.
6.
12 SS 94#
SG Blowdown Sampling s10Sec.
7.
13 SS 94#
SG Blowdown Sampling s10Sec.
8.
14 SE 94#
SG Blowdown Sampling s10Sec.
F.
CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF 1,
1 VC 1 Purge Supply s2Sec.
2.
1 VC 2 Purge Supply s2Sec.
3.
1 VC 3 Purge Exhaust s2Sec.
4.
1 VC 4 Purge Exhaust s2Sec.
5.
1 VC 5*
Pressure - Vacuum Relief s2Sec.
6.
1 VC 6*
Pressure - Vacuum Relief s2Sec.
SALEM - UNIT 1 3/4 6-15 Amendment No.158
6 TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (Seconds)
G.
MANUAL
- 30. 11 SS 181*
Poet LOCA Sampling Not Applicable
- 31. 11 SS 182*
Post LOCA Sampling Not Applicable
- 32. 11 SS 188*
Post LOCA Sampling Not Applicable
- 33. 11 SS 189*
Post LOCA Sampling Not Applicable
- 34. 13 SS 181*
Post LOCA Sampling Not Applicable
- 35. 13 SS 182*
Post LOCA Sampling Not Applicable
- 36. 13 SS 184*
Post LOCA Sampling Not Applicable
- 37. 13 SS 185*
Post LOCA Sampling Not Applicable
- 38. 11 VC 17*
Post LOCA Sampling Not Applicable
- 39. 11 VC 18*
Post LOCA Sampling Not Applicable
- 40. 11 VC 19*
Post LOCA Sampling Not Applicable
- 41. 11 SF 20*
Post LOCA Sampling Not Applicable
- 42. 12 VC 17*
Post LOCA Sampling Not Applicable
- 43. 12 VC 18*
Post LOCA Sampling Not Applicable
- 44. 12 VC 19*
Post LOCA Sampling Not Applicable
- 45. 12 VC 20*
Post LOCA Sampling Not Applicable
- 46. 11 CS 2+
Containment Spray Not Applicable
- 47. 12 CS 2+
Containment Spray Not Applicable H.
CHECK 1.
1 CV 74 CVCS-Charging Line Not Applicable 2.
1 CV 296 CVCS-RCP Seals Not Applicable 3.
1 CC 119 Component Cooling to RCP Not Applicable 4.
1 CC 186 Component Cooling to RCP Not Applicable 5.
1 CC 208 Component Cooling to RCP Not Applicable 6.
11CS 48 Containment Spray Not Applicable 7.
12CS 48 Containment Spray Not Applicable B.
1 DR 30 Demineralized Water System Not Applicable 9.
1 FP 148 Fire Protection System Not Applicable
- 10. 1 NT 26 Pressurizer Relief Tk. - Nitrogen Conn. Not Applicable
- 11. 1 NT 34 Accumulator Nitrogen Supply Not Applicable
- 12. 1 SA 119 Compressed Air Supply Not Applicable
- 13. 1 WR 81 Pressurizer Relief Tank - Primary Not Applicable Water Conn.
- 14. 11CA 360 Instrument Air Supply Not Applicable
- 15. 12CA 360 Instrument Air Supply Not Applicable
- 16. 11BF 22#
Main Feedwater Not Applicable 17, 12BF 22#
Main Feedwater Not Applicable
- 18. 13BF 22#
Main Feedwater Not Applicable
- 19. 14BF 22#
Main Feedwater Not Applicable
- May be opened on an intermittent basis under administrative control.
- Not subject to Type C leakage tests.
+ Normally closed motor operated containment isolation valve. Valves open on Phase B isolation.
SALEM - UNIT 1 3/4 6-17 Amendment No.158
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY p0CKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.139 License No. DPR-75 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 March 28, 1994, 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: (1) 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 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:
. =.
- 2' -
e (2) Igsat cal Soecifications and Environmental Protection Plan The Technical Spec lfications contained in Appendices A and B, as revised through Amendment No.139, are hereby incorporated.in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
This lic nse 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 CL. LJ John r. 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: October 20, 1994 9
5
i l
ATTACHMENT TO LICENSE AMENDMENT N0.139 FACILITY OPERATING LICENSE N0. OPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 6-19 3/4 6-19 i
)
a TABLE 3.6-1 (Contd.)
CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (Seconds)
G.
MANUAL (Contd.)
- 30. 21 SS 181*
Post LOCA Sampling Not Applicable
- 31. 21 SS 182*
Post LOCA Sampling Not Applicable
- 32. 21 SS 188*
Post LOCA Sampling Not Applicable
- 33. 21 SS 189*
Post LOCA Sampling Not Applicable 34, 23 SS 181*
Post LOCA Sampling Not Applicable
- 35. 23 SS 182*
Post LOCA Sampling Not Applicable
- 36. 23 SS 184*
Post LOCA Sampling Not Applicable 37, 23 SS 185*
Post LOCA Sampling Not Applicable
- 38. 21 VC 17*
Post LOCA Sampling Not Applicable
- 39. 21 VC 18*
Post LOCA Sampling Not Applicable
- 40. 21 VC 19
- Post LOCA Sampling Not Applicable 41, 21 SF 20*
Post LOCA Sampling Not Applicable
- 42. 22 VC 17*
Post LOCA Sampling Not Applicable
- 43. 22 VC 18*
Post LOCA Sampling Not Applicable 44, 22 VC 19*
Post LOCA Sampling Not Applicable
- 45. 22 VC 20*
Post LOCA Sampling Not Applicable 46, 21 CS 2+
Containment Spray Not Applicable 47, 22 CS 2+
Containment Spray Not Applicable H.
CHECK 1.
2 CV 74 CVCS-Charging Line Not Applicable 2.
2 CV 296 CVCS-RCP Seals Not Applicable i
2 CC 186 Component Cooling to RCP Not Applicable 5.
2 CC 208 Component Cooling to RCP Not Applicable 6.
21 CS 48 Containment Spray Not Applicable 7.
22 CS 48 Containment Spray Not Applicable 8.
2 DR 30 Demineralized Water System Not Applicable 9.
2 FP 148 Fire Protection System Not Applicable
- 11. 2 NT 34 Accumulator Nitrogen Supply Not Applicable
- 12. 2 SA 119 Compressed Air Supply Not Applicable 13, 2 WR 81 Pressurizer Relief Tank - Primary Not Applicable Water Conn.
14.
21 CA 360 Instrument Air Supply Not Applicable 15.
22 CA 360 Instrument Air Supply Not Applicable 16.
21 BF 22#
Main Feedwater Not Applicable 17, 22 BF 22#
Main Feedwater Not Applicable 18.
23 BF 22#
Main Feedwater Not Applicable 19.
24 BF 22#
Main Feedwater Not Applicable May be opened on an intermittent basis under administrative control.
- Not subject to Type C leakage tests.
- Either valve 2 CV 68 or 2 CV 69 must be OPERABLE.
Normally closed motor operated containment isolation valve. Valve opens
+
on Phase B isolation.
SALEM - UNIT 2 3/4 6-19 Amendment No.139 i