ML20211E702
| ML20211E702 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/15/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20211E708 | List: |
| References | |
| NPF-57-A-102 NUDOCS 9709300211 | |
| Download: ML20211E702 (5) | |
Text
1
.,k UNITED STATES p
g f';
NUCLEAR REGULATORY COMMISSION j'
WASHINGTON. 0.C. 3ee06 4001 e...../
PllBLIC SERVICE ELECTRIC & GAS COMPANY
+4 ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50 354 HOPE CREFg GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-57 1.
The Nuclear Regulatory Commisrion (the Comission) has found that:
A.
The ap)11 cation for amendment filed by the Public Service Electric
& Gas Company (PSE&G) dated July 3, 1997. 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 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
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 NPF-57 is hereby amended to read as follows:
NR DON 15 b54 F
7.
4 -
(2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised thraugh Amendment No.102, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE1G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuan'e.
FOR THE NUCLEAR REGULATORY COMMISSION J hr/h Stolz, Direct r ject Directorate
-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 15, 1997
4
/TTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50 354 Replace the followin the attached pages. g sages of the Appendix "A" Technical Specifications with T1e revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert i
. 1 3/4 6 23 3/4 6 23 3/4 6 28 3/4 6 28 t
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TABLE 3.6.3-1 (Continued)
PRIMARY COtfrAI*: MENT ISOLATION VALVES MAXIMtm ISOLATION PENETRATION TIM VALVE FU8BCTICIf AltD NLMBER NUMBER (Seconds) le0TE(S)
PEID 8.
Group 8 - Torus Water Cleanup (TWC) System (a) TWC Suction Isolation valves M-53-1 Outside:
HV-4680 (EE-V003)
P223 45 4
HV-4681 (EE-V004)
P223 45 4
(b) TWC Return Isolation Valves M-53-1 Outside:
HV-4652 (EE-V002)
P222 45 4
HV-4679 (EE-V001)
P222 45 4
9.
Group 9 - Drywell Sumps (a)
Drywell Floor Drain Susp Discharge Isolation valves M-61-1 I-Inside: HV-F003 (HB-VOOS)
P25 30 3
i Outside: HV-F004 (HB-V006)
P25 30 3
Inside: 1HBPSV-11701 P25 NA 3
l (b)
Drywell Equipment Drain Supp Discharge Isolation valves M-61-1 Inside: HV-F019 (HB-V045)
P26 30 3
Outside: HV-F020 (HB-V046)
P26 30 3
4 Inside: 1H3PSV-11702 P26 NA 3
1 10.
Group 10 - Drywell Coolers (a)
Chilled Water to Drywell Coolers Isolation valves M-87-1 Inside:
Loop A: HV-9531B1 (GB-V081)
P8B 60 3
[
Loop B HV-9531B3 (GB-V083)
P38A 60 3
HOPE CREEK 3/4 6-23
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Aunendment No.102 i
TABIK 3. 6. 3 -1 (Continued)
PRIMART CONTAINMENT ISOEATION VALVES MiutIM)M ISOEATION PENETRATICII TIfE VALVE FLEICTION ABC EstNBER NLWWER ISE:ssads). IIDTE(S)
IMR
- 16. Group 16 - Reactor Auxiliaries Cooling System (RACS)
(a)' RACS Supply Isolation V.sives M-13-1 Inside: HV-2554 (RD-V020)
P29 45 3
Outside: MV-2553 (ED-V019)
P29 45 3
Inside: 1EDPSV-11699 P29 NA 3
l 1
(b) RACS Return Isolation valves M-13-1 Inside: HV-2556 (ED-V022)
P30 45 3
Outside: HV-2555 (ED-V021)
P30 45 3
Inside: 1EDPSV-11700 P30 NA 3
l
- 17. Group 17
SV-J004A-1 (SE-V026)
P34A 15.
3 SV-J004A-2 (SE-V027)
P34B
'15 3
/
SV-J004A-3 (SE-V028)
P34C 15 3
t "SV-J004A-4 (SE-V029)
P34D 15-3 SV-J004A-5 (SE-V030)
P34E 15 3
i (b) TIP Purge System Isolation valve M-59-1 Outside:
HV-5161 (SE-V004)
P34F 15 3
- 18. Group Reactor Coolant Pressure Boundary (RCPB)
Leakage Detection System (a) Drywell Leak Detection Radiation Monite.ing System (DLD-RMS) 4 Inlet Isolation valves M-25-1 Outside:
MV-5018 (SK-V005)
J8C 45 3
i HV-4953 (SK-V006)
JSC 45 3
MPE CREEK 3/4 6-28
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