ML20205N694
| ML20205N694 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/21/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205N696 | List: |
| References | |
| NUDOCS 8811040287 | |
| Download: ML20205N694 (11) | |
Text
_ _ _.
/"
UNITED STATES NUCLEAR REGULATORY COMMISSION
{
W ASHINGTON. O. C. 20e64 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM GENERATING STATION, UNIT NO. 1 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. OPR-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 August 6, 1985 and supplements dated August 29, 1986 and August 16, 1988 complies with the standards and requireme9ts of the Atomic Energy Act of 1954, as amended (the Act), ano 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 L
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 l
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 l
satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and i
paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby i
amended to read as follows:
P l
2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 89, 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.
FOR THE Nilet.E/R REGULATORY COMMISSION
/S/
Walter R. Butler, Director Prcject Directorate I-2 I
Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
Octouer 21, 1988 l
1 I
pak 'ghA P01-2/PM OGC PDI-2/0 h
p?pfen JStone:tr J [4 l<-W //
W8utler 9 \\)/88 h' /2 488 jl/\\/88
/
88
2 (2) Technical Specifications and Enviromental Protection Plan The Technical Specificatiols contained in Appendices A and B, as revised through Amendment No. 89. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This Itcense amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY CODNIS$10N
/4g?7i? 8L 5
Valter R. Butler Director Project Directorate I 2
)
Division of Reactor Pro,iects !/II i
Attachment:
4
)
Changes to the Technical Specifications J
Date of Issuance: October 21, 1988 l
1 f
i 1
- 1 ATTACHMENT TO LICENSE AMEN 0 MENT NO. 99 FActLITY OPERATING LICENSE NO. OPR-70 i
DOCKET NO. 50-272 Revive Appendix A as follows:
Ree.ve Page Insert Pages l
3/4 6-5 3/4 6-5 i
3/4 6-5a
(
6 t
l
?
Y i
i
8 i
i l'
CONTA!hMENT SYSTEMS CONT 4 thMENT AIR LOCKS LIMITING CONDIT0N FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
4.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of 10.05 La at design pressure (47.0 psig).
I APPLICABILITY: MODES 1, 2. 3 and 4 ACTION l
With an air lock inoperable, restore the air lock to OPERABLE status L
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or de in at least HOT STAh06Y 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 />.
l t
SURVEILLANCE REQUIREMENTS 1
1 4.6.1.3 Each containrent air lock shall be demonstrated OPERABLE:
i.
- a. '8y pressurizing the volure between the airlock door gaskets to 110.0 psig and checking for an extrapolated ** seal leakaga rate equal to or less tnan 0.01 La.
1.
Af ter each opening, except when used for multiple entries, 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 />.
l h
I 2.
Af ter performing maintenance which could affect the airloct Goor gaskets sealing capability.
l l
3.
Prior to estabitshing containment integrity, b.
By conducting an overall air lock leakage test at design l
pressure (47.0 psig) and verifying the overall air leakage rate 1s within its limit:
1.
At least once per six months p.
[
t p
SALEM - UNIT 1 3/4 6 3 Amendrent No. 89
}
t i
l E
I
e e
CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS SURVEILLANCE RE0J!REMENTS (Continueo) 2.
Prior to establishing containment integrity when maintenance that could affect the airlock Sealing capability was performed and the maintenance affects components other than the eor gaskets,* and
- c. At least once imr 6 cenths oy v'erifying that only one door in each air lock can be opened at a time.
Energtion to Appenoix "J" of 10 CFR $0.
" The nessured laakage at the test pressure (10 psig) shall be mittplied by an extrapolation factor of 9.1 to determine what the seal leakage flow rate would be if tested at destgr) pressure (47.0 plig). This extrapolated seal leakage rate shall be less than or equal to 0.01 La.
ine provisions of Specification 4.0.2 are not applicable.
1 i
I l
i 3/4 6-Sa W W nt No.
M SALEM UMil 1 s
l
p**%g'g
/
/
UNITED STATES l'
NUCLEAR REGULATORY COMMISSION e
g t
WASHING TON. D. C. 20006 PUBLIC S2RVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY i
O_ELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY 00CKET NO. 50-311 SALEM GENERATING STATION, UNIT NO. 2 r
AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 62 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 August 6, 1985 and supplements dated August 29, 1986 and August 16, 1988 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 1
provisions of the Act, and the rules and regulations of the Commission; C.
Inere 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 regulaticns set forth in 10 CFR Chapter I; I
0.
The issuance of this amendment will not be inimical to the conson defense and security or to the health and safety of the public; and l
E.
The issuance of this amenoment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this licenss caendment, and
(
paragraph 2.C.(2) of Facility Operating License No. UPR-75 is hereby amended to read as follows:
l
2-(2) Technical Specifications and En 'rontaental Protection Plan T5a Technical Specifications contained in Appendices A and B, as revised through Ar.endment No. 62, are hereby incorporated in the license.
The licensee shall opurate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
3 FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director i
Project Directorate I-2
)
Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 21, 1988 I
i i
l l
I
- Previously Concurred ly PDI-2/PM*
OGC" POI-2/0*
Iq sn JStone:tr 5N Le ul/ 5 WButler e.{'88 10/13/88 10/20/88 10/21/88
(
-m
.g.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 62, 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.
FOR THE NUCLEAR REGULATORY C0$NIS$10N Y-V Walter R. Butler, Ofrector Project Directorate I-2 DivisionofReactorProjectsI/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 21, 1988
i s.
}
ATTACHMENT TO LICENSE AMENONENT NO. 62 FACILITY OPERATING LICEM E N0. OPR-75 i
I DOCKET NO. 50 311 l
Revire Appendix A as follows:
Remov, Peg, Insert Pace 3/4 6 5 3/4 6-5 i
i i
l 5
l 1
I l
I I
I I
l l
f l
i I
i I
i CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS
$URVEILLANCE RtWIREMENTS (Continued)
- a. 'By pressurizing the volume between the airlock door gestets to
{
y,10.0 psig and checking for an extrapolated" seal letkage rate equal to or less than 0.01 L
- a 1.
After each opening, except when used for mitiple entries, 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 />.
2.
After performing natntenance which could affect the airlock door gaskets sealing capability.
i 3.
Prior to establishing containrent integrity, b.
By conducting an overall air lock leakage test at design pressure (47.0 psig) and verifying the overall air leakage rate is within its limit
- 1.
At least once per six nonths f.
l t
2.
Prior to establishing containrent integrity wnen maintenance that could affect the airlock sealing capattitty was performed and the maintenance affects components other than the coor gaskets.' and c.
At least once per 6 senths by verifying that only one door in each air lock can be opened at a tim.
i r
1
~*~ E meret to n to Appeno t a N' o f 10 CFR 60.
l
> 10 psig) sna11 be
" The matureo leakage at the test pressure (T to determine wnat the mitiplied by an entrapolation factor of 9.
seal leakage flow rate sculd be if tested at design pressure (47.0 I
psig). This entrapolated seal leakage rate shall t., less than or equal to 0.01 La t
l
- The provisions of Specification 4.0.2 are ret applice.le.
[
r 1
SALEM UNIT 2 3/4 6-5 Amendnent No. 62 i
[
1 i
!