ML20054E381
| ML20054E381 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-70-A-044, DPR-70-A-44, DPR-75-A-008, DPR-75-A-8) |
| Issue date: | 05/25/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054E376 | List: |
| References | |
| NUDOCS 8206110154 | |
| Download: ML20054E381 (11) | |
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UNITED STATES o,,
NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D. C. 20666 r,
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and' Atlantic City Electric Company (the licensees) dated Mai 17, 1982, 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; erate in confomity with the application, The facility will op'e Act, and the rules and regulations of B.
the provisions of th the Comission; 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; 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 cf this amendment is in accordance with 10 CFR Part 51 of the Commission's regolations and all applicable requirements,-
have been satisfied.
DESIGUATED ORIGINAL Certified By 8206110154 820525
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PDR ADOCK 05000272 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the at'tachment to this ifcense amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44 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 the date of~its issuance.
1 FCI THE NUCLEAR REGULATORY f
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Attachment:
Changes to the Technical Specifications j
Opte of Issuance: May 25,1982 l
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UNITED STATES NUCLEAR REGULATORY COMMISSION a
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY _
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 r
AMENDMENT TO FACILITY OPERATING LICENSE J
Amendment No. 8 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and ' Atlantic City Electric Company (the licensees) dated May 17, 1982, 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; f
B.
The facility will operate in conformity with the application, tha provisions of the Act, and the rules and regulations of
-j the Commission; t
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; 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 Commission's regulations and all applicable requirements have been satisfied.
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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 License No. OPR-75 is hereby amended to read as follows:
(2) Technical Saecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
8. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificaticas.
I 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ma
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yief Operating Reac or i Branch #1 Division of Li n [ing Changes to the Technical Specifications Date of Issuance:
May 25. -1982 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. DPR-70_
DOCKET NO. 50-272
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Revise Appendix A as follows:
Insert Page Remove Page 3/4 5-5 3/4 5-5 3/4 5-Sb
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS ' Continued)
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c.
By a visual inspection which verifies that no loose debris (r'ags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditior.s.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
A visual inspection of the containment sump and verifying that 1
the subsystem suction inlets are not restricted by debris and' i
that the sump components (trash racks, screens, etc.) show no
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evidence of structural distress or corrosion.
j e.
At least once per 18 months, during shutdown, by:
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1.
Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.
l 2.
Verifying that each of the following pumps start automatically upon receipt of a safety injection test signal:
a)
Centrifugal charging pump b)
Safety injection pump c)
Residual heat removal pump 4
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Ir SALEM - UNIT 1 3/4 5-5 Amendment No. 44 l1
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- i. The automatic isolation and interlock function of the RHR System shall be verified within the seven (7) days prior to placing the RHR System in service for cooling of the Reactor Coolant System, This shall be done by verifying that valves RH1 and RH2 close upon insertion of a test signal corresponding to a reactor coolant pressure of 580 pstg or less, and that, with a test signal corresponding to a reactor coolant pressure of 580 psig or greater, that the valves cannot be opened, u
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SALEM UNIT 1 3/4 5-5b Amendment No. 44 w
1 ATTACHMENT TO LICENSE AMENDMENT N0. 8 l,
FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311
,j Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 5-5 3/4 5-5 3/4 5-6 3/4 5-6 3/4 5-6a 3/4 5-6a h
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EMERGENCY CORE C00LI$G SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
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c.
By a visual inspection which verifies that no loose debris (r'ags, -
trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and Of the areas affected within containment at the completion of 2.
each contiinment ent'ry when CONTAINMENT INTEGRITY is established.
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d.
At least once per 18 months by:
1.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and' that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
e.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path actu'ates to its correct position on a saf..ety injection test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a safety injection test signal:
a)
Centrifugal charging pump b)
Safety injection pump c)
. Residual heat removal pump l
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SALEM - UNIT 2 3/4 5-5 Amendment No. 8
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F.MERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) f.
By verifying that each of the following pumps develops the indi'cated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:
1.
Centrifugal charging pump 2 2400 psig 2.
Safety Injection pump t 1425 psig 3.
Residual heat removal pump 2 165 psig g.
By verifying the correct position of each of the following ECCS throttle valves:
1.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
I 2.
At least once per 18 months, i
Valve Number-Valve Number 21 SJ 16 21 SJ 138 22 SJ 16 22 SJ 138 l
23 SJ 16 23 SJ 138 1
24 SJ 16 24 SJ 138 j
21 SJ 143 F
22 SJ 143 A
23 SJ 143 1
24 SJ 143 J
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h.
By performing a flow balance test, during shutdown, following j
completion of modifications to the ECCS subsystems that alter the j
subsystem flow characteristics and verifying that:
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1.
For safety injection lines, with a. single pump running:
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a)
The sum of the injection line flow rates, excluding the j
line with the highest flow rate, is > 463 gpm, and b)
The total pump flow rate is 1650 gps.
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2.
For centrifugal charging pump lines, with a single pump i!
rur.ning:
a)
The sum of the injection line flow rates, excluding the j.
line with the highest flow rate, is > 346 gpe and r
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b)
The total pump flow rate is 1550 gpm.
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SALEM - UNIT 2 3/4 5-6
- Amendment No. 7 8
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f.
The automatic isolation and interlock function of the RHR System shall be verified within the seven (7) days prior to placing the RHR System in service for cooling of the Reactor Coolant System. This shall be done by verifying that valves RH1 and RH2 close upon insertion of a test signal corresponding to a reactor coolant pressure of 580 psig or less, and that, with a test signal corresponding to a reactor coolant pressure of 580 psig or greater, that the valves cannot be opened.
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, SALEM UNIT 2 3/4 5-6a Amendment No. 8 i
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