ML20058E057
| ML20058E057 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/30/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058E061 | List: |
| References | |
| NUDOCS 9011070008 | |
| Download: ML20058E057 (7) | |
Text
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g UNITED STATES c
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3 NUCLEAR REGULATORY COMMISSION J
MSWNO TON. O. C. 20556 S
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PUBLIC. SERV!CE ELECTRIC & GAS COMPANY Ptf!LADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCFAT NO. 50-311 L
SALEM GENERATING STATION. UNIT NO. 2 j
AMENDMENT TO FACILITY OPERATING LICENSE P"
Amendment No.91 r
License No. DPR-75 b
- 1.. ^that:
The Nuclear Regulatory Comissis (the Comission or the NRC) has found l
i A.
The application for. amendment filed by the Public Service Electric &
3 Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated k
April 4, 1990, and, supplemented by letters dated April 12, 1990,.
l
. April.20, 1990 and May 7, 1990, complies with the standards and
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requirements of the Atomic En6rgy Act of 1954, as amended (the Act),
j 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)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health _and safety of the public, and (ii) that such activities will be conducted I
in compliance with the Ccanission's regulations set forth in 10 CFR Chapter It-1, 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.
i E.
The issuarice of this amendment is in accordance with 10 CFR Part 51 of the Comission's' regulations and all applicable requirements have been i
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 paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
u 9011070008 900530 PDR ADOCK 05000311 P
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(2) Technical Specifications and Enviror.inental Protection Plan i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.-
91, 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 COMMISSION e
/s/
Walter R. Butler,-Director Project Directorate I-2 Division of Reactor Projects
'I/II
Attachment:
Changes to the Technic'al Specifications Date of Issuance: May 30, 1990 4
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NAMES :M0'Brien i
WButler DATE' :05/
/90-
- 05/11 /90
- 05/SS/90
- 05/29/90 1
0FFICIAL RECORD CODY
. Document Name: SA.EM AMEND 76415
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1.o (2)' Technical' Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 91, are hereby incorporated in the license. The licensee shall o
'the Technical Specifications. perate the facility in accordance with 3.
r 4 license amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION 6
f Walter R. Butler, Director.
Project Directorate I-2
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-Division of Reactor Projects - I/II
Attachment:
- Changes ts the Technical Specifications Date of Issuance:. May 30, 1990 4
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ATTACHMENT TO LICENSE AMENDMENT NO. - 91 i
.i-FACILITY OPERATING LICENSE NO. DPR-75 1
DOCKET NO. 50-311 I
Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 7-10 3/4,7-10
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4 TAf)LE 3. 3. $ / Continued)
.s ENCINEERED SAFETY TEATL'REE REEPONSE TIMEE c
m.
INITTATINC $fCNAL AND FL'NCTION RESPONSE TIME IN SECONBS i
3.-
Pressurinar Pressura Low a.
Safety Injection (ECCS)
S 27.0(1)/12.0(2) b.
Reactor Trip (from SI) 5 2.0 c.
Feedwater Isolation s 7.0 d.
Containment Isolation Phase "A" s 18.0(2)
Containment Venti 1a' tion Isolation Not Appliccble e.
f.
Auxiliary Feedwater Pumps.
S 60 I
g.
Service Water Systes s 49.0(1)/13.0( }
l 4
Differential Pressure Between Steam Linee Hirh
-1 i
a.
Safety Injection (ECCS) s 12.0(2)/22.0(3) b.
Reactor. Trip (from SI)
$ 2.0
' c.>
Teodwater Isolation s 7.0 d.,
Containment ~ Isolation Phase "A"
$ 17.0(2)/27.0(3) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps s 60
. g.
Service Water Systea 5 13.0(2)/48.0(3) l3 l'
'5.
' Steam Flow in two Steam Lines Hiah Coincident l
with Tava
-Low-Low
)
l II/25.75(3)
- a.
Safety Injection (ECCS) s 15.75 b.
Reactor Trip (from SI) s 5.75 y
- c.
~ Feedwater Isolation s 10'75 lJ1
. d.. Containment Isolation Phase "A" s 20.75(2)/30.75(3) y, e.
Containment Ventilation Isolation Not Applicable
[
f.
Auxiliary Feedwater Pumps s 61.75 g./ Service. Water Systen-s 15.75(2)/50.75(3) h Steam Line Isolation s 10.75*
c 513.75 seconds until restart following the sixth refueling outage.
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SALEM - UNIT 2 3/4 3 29 Amendment No.
91 1
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3 TABLI 3.3 5 (Continued)
ENCINKrafn SAFETY FEATURES RFCPONSE TIMES INITIATINC SICMAL AND FUNCTION t
RESPONSE TIME IN SECONDS 6.
Steam Flow in Two Steam Linea Himh Coincident with Steam Line Pre s s ura - Low I
a.
Safety Injection (ECCS)
$ 12.052)/22.0(3) b.
Reactor Trip (from SI)
$ 2.0 c.
Feedwater Isolation s 7.0 t
d.
Containment Isolation Phase "A" s 17.0(2)/27.0(3) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary F9edwater Pumps s 60 g.
Service Water System s14.Q(2)/48,0(3) h.
Steam Lire Isoletion s 8.0 1
7.
Containment Pressure-Hith Hiah a.-
Containment Spray s 45.0
- b.
Containment Isolation Phase "B" Not Agplicable c.
Steam Line Isolation s 7.0 d.
Containment Fan Cooler s 40.0 8.
' Steam Canarator Vatar' Level--Hith Himh 4R a.-
$ 2.5
- b..
Feedwater Isolation s 11.0 9.
Steam cenerator Vater Laval - Low Low t
_a.:
Motor Driven Auxiliary Feedwater s 60.0 Pumps (4)
I b.
Turbine Driven Auxiliary Feedwater s 60.0 Pumps (5) a L
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$10.0 seconds until restart following the sixth refueling outage, t
i l-SALEM UNIT 2 3/4 3 30 Amendment No.
91 t
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' PMNT SYSTEWS MAIN STEAM LINE ISOMTION VALVES LIMITING CONDITION FOR' OPERATION U"
- 3. 7.1. 5 - Each main steam line isolation valve shall be OPERABLE.
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APPLICABILITY: MODES 1, 2 and 3.
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ACTION!
MODES 1 -' With one main steam line isolation valve inoperable, POWER OPERATION may continue provided.the Janperable valve 14 either restored to OPERABLE status or closed w.tr.in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; 1
Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
MODES 2 With one main' steam line isolation valve inoperable, subsequent-i and 3 operation in MODES 1, 2 or 3 may proceed provided; a.
The isolation valve-is maintained closed.
h
.b.
The provisions of specification'3.0.4 are not applicable.
Otherwisa, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
dk SURVEILLANCE REQUIREMENTS 4;7.1.$1 Each main steam line isolation valve shal OPERABLE by verifying full closure within $ seconds} be demonstrated when tested pursuant to l
Specification 4.0.5.
8-seconds until restart following the sixth refueling outage.
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j SALEN'- UNIT 2 3/4 7 10 Amendment No.
91 l:
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