ML20052C810
| ML20052C810 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/19/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052C811 | List: |
| References | |
| NUDOCS 8205050567 | |
| Download: ML20052C810 (11) | |
Text
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NUCLEAR REGULATORY COMMISSION '
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s PUBLIC SERVICE ELECTRIC AND GAS COMPANf PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER ~AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0; 50-272' SALEM NUCLEAR GENERATING STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE, 41 Amen'dment No. f License No.'DFR-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 E'ectric Company (the licensees) dated January 15, 1982, complies with the standards ard. require-ments of the Atoinic inergy Actiof 1954, as amended (the Act) and the Commission's rules and regulations set' forth?!n 10 CFR Chapter I; 1:
B.
The facility will operat5 in ' conformity +ith the application, the provisions ~of the Act, and the rules -and regulations of s
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 Commission's regulations; 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.
8205050567 820419 PDR ADOCK 05000272 P
,, 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 License No. DpR-70 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 41, 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.
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Attachment:
Changes to the Technical Specifications Date of Issuance: April 19,1982 I
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY
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DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. DPR-75 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 January 15, 1982, complies with the standards and require-ments 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 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; 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 Comission's regulations and all applicable requirenents have been satisfied.
,, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license j
amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
7, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificaitons.
3.
This license amendment is effective as of the date of its issuance.
f THE NUC ARjR GULATORY COMMISSION n
- arga, Operating Reactors B nch No. 1 Division of Licensin \\
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Attachment:
Changes to the Technical Specifications Date of Issuance: April 19, 1982
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ATTACHMENT TO LICENSE AMENDMENT NO. 41 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
i Remove Pages Insert Pages 3/4 6-8a 3/4 6-8a 3/4 6-13 3/4 6-13 3/4 6-16 3/4 6-16 f
f-
l CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM WMITING CONDITION FOR OPERATION 3.6.1.7 The containment purge soply and exhaust isolation valves
- shall be closed. (valves imobilized in shut position with control air to valve operators isolated snd tagged out of service).
APPUCABILITY: MODES 1, 2, 3, and 4 ACTION:
With one containment. purge supply and/or exhaust isolation valve open, close the open valve (s) within one hour or be in at least NOT 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 fo11 swing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REOUIREMENTS 4.6.1.7 The containment purge supply and exhaust isolation valvas shall be detemined closed at least once per 31 days.
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l "The contairment pressure-vacuum relief isolation valves any be opened on an intamittant basis, under aministrative control, as necessary to satisfy the requirement of specification 3.6.1.4.
SALEM - WIT 1 3/4 6 sa Amendmer;t No. 41 l
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
W 4'.6.3*.1'.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated l
OPERABLE during the COLD SHUTDOWN or REFUELING ICDE at least once per 18 months by:
Verifying that on a Phase A containment isolation test signal, each a.
Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each i
Phase B isolation valve actuates to its isolation position.
l Verifying that on a feedwater isolation tabr, signal, each feedwater c.
isolation valve actuates to its isolation position.
Verifying that on a Containment Purge and Pressure-Vacuum Relief d.
isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position.
l f
4.6.3.1.3 At least once per 18 month, verify that on a main steam isolation test signal, each main steam isolation valve specified in Table 3.6-1 actuates i
to its isolation position.
i 4.6.3.1.4 The isolation time of each power operated or automatic valve of l
Table 3.6-1 shall be determined to be within its limit when tested pursuant to i
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 8 and C penetrations, the combined i
l 1eakage rate is less than or equal to 0.60L,.
4.6.3.1.6 A pressure drop test to identify encoessive degradatica of resilient valve alc shall be conducted on th&~:
Q:ntaiment PLIrge Sug5 ply and Exhaust Isolation Vhlves at 2amst once a.
per 6 months.
b.
Omtainnent Prersure - Vhcmaan WWF Tan 1stion val 1ves at least anoe per 3 months.
Amendment No. 41
(
SALEM - UNIT 1 3/4 6-15
TABLE 3.6,1___(Cont.inued)
CONTAINMENT 1501AT10N VALVES r
M9 VALVE NUMBER filNCTION ISOLATigTIME_
g C.
MP'M STEAM ISOLATION M
1.
11 MS 7f Main Steam Drain
< 10 Sec.
2.
12 MS 7#
Main Steam Drain 7 10 Sec.
3.
13 MS 7f Main Steam Drain 7 10 Sec.
4.
14 MS 7f Main Steam Drain 7 10 Sec.
5.'11 MS 18f Main Steam Bypass
[10Sec.
< 10 Sec.
6.
12 MS 18f Main Sti?am Ilypass
[10Sec.
7.
13 MS 18f Main Steam Hypass 8.
14 MS 18f Main Steam Dypass 1 10 Sec.
D.
FEEDWATER ISOLATION M
1.
11 BF 19f Main fecttwater Isolation
< 8 Sec.
2.
12 8F 19f Main feedwater Isolatiswi
[8Sec.
g 3.
13 8F 19f Main feedwater Isolation 1 8 Sec.
4.
14 8F 19f Main Feedwater Isolation
< 8 Sec.
5.
11 8F 40f' Main feedwater Isolation 7 8 sec.
6.
12 BF 40f Main feedwater Isolation 7 8 Sec.
7.
13 8F 40f Main feedwater Isolatioti 7 8 Sec.
8.
14 BF 40f Main feedwater Isolation
[11Sec.
E.
CONTAllMDIT PURGE AND PRESSURE-VACUUM RElitf a
< 2 Sec.
i 1.
I VC 1 Purge Supply 7 2 Sec.
2.
I VC 2#
Pierge supiily 7 2 Sec.
3.
I VC 3#
Purge 1 xlianst 7 2 Sec.
E 4.
I VC 4 Purge l'xhaust S.
I VC Sa Pressurc-Vacutse Relief 7 2 Sec.
3 6.
I VC 6#*
P c',sure-Vacuum Re1lef
[2Sec.
O
ATTACHMENT TO LICENSE AMENDMENT N0. 7 FACILITY OPERATING LICENSE N0. DPR-75 l
DOCKET N0. 50-311 r
Revise Appendix A as follows:
Remove Pages Insert Pages 1
3/4 6-9 3/4 6-9 i
3/4 6-15 3/4 6-15 1
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4 I
I 4
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_ CONTAINMENT SYSTEMS CONTAINhENT VENTILATTON SYSTEM i
LIMITING CONDITION FOR OPERATION l
3.6.1.7 The containment purge supply and exhaust isolation valves" shall be closed. (valves inanobilized in shut position with control air to valve operators
]
isolated and tagged out of service).
J APPLICA8ILITY: MODES 1, 2, 3. and 4.
ACTION:
With one containment. purge supply and/or exhaust isolation valve open, close the open valve (s) within one hour or be in at least NOT 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 />.
i SURVEILLANCE REOUIREMENTS I
4.6.1.7 The containment purge supply and exhaust isolation vaivas shall be datamined closed at least onca per 31 days.
"The containment pressure-vacuum relief isolation valves any be opened on an intamittent basis,under administrative control, as necessary to satisfy the requirement of Specification 3.6.1.4.
SALEM - LMIT 2 2/4 6-9 Amendment No. 7
i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 4.6.3.2 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 centainment 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.
Verifying that on a feedwater isolation test signal, each feedwater isolation valve actuates to its isolation position.
d.
Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position.
4.6.3.3 At least once per 18 month, 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.
4.6.3.4 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.
~_
4.6.3.5 Each containment purge isolation valve shall be demonstrated OPERABLE r
l 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 0.60L,.
4.6.3.6 A pressure drop test to identify excessive degradaticm of resilient valve seals shall be conducted on the :
(
a.
Cbntainment Purge Sugiply and Exhaust Isolation Valves at least ance per 6 months.
b.
Cbntairsent Pressure - Var,3=n kliaf Isolation Valves at least once per 3 nonths.
SALEM - UNIT 2 3/4 6-15 Amendment No. 7