ML18092A394
| ML18092A394 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/15/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18092A395 | List: |
| References | |
| LCR-84-12, NUDOCS 8411210215 | |
| Download: ML18092A394 (5) | |
Text
PStiG*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref:
LCR-8 4-12 October 15, 1984 Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission Washington, D. c.
20555 Attention:
Mr. Steven A. Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES UNIT NOS. 1 AND 2 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment and our analyses of the changes to Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2.
This amendment request consists of a revision to Technical Specifications, Appendix A, Section 3.4.2, regarding reactor coolant system safety valves while shutdown.
In accordance with the fee requirements of 10CRF170.21, a check in the amount of $150.00 is enclosed.
Pursuant to the requirements of 10CFR50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below.
95-2168 (80 MJ 11-82
Mr. Steven 10/15/84 This submittal includes three (3) signed originals and forty (40) copies.
Enclosure C
Mr. Donald c. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector Sincerely, E. A.
Manager -
Nuclear Licensing and Regulation Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, New Jersey 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801
Ref: LCR-84-12 STATE OF NEW JERSEY )
)
ss:
COUNTY OF SALEM COUNTY OF SALEM
)
RICHARD A. UDERITZ, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our Request for Amendment dated October 15, 1984, are true to the best of my knowledge, information and belief.
d,£4*~
RICHARD A. UDERIT Subscribed and sworn to before me this /.a;C.
In:~~
day of ~
, 1984 Notary Public of New Jersey DONNA G. HITCHNER NOTARY PUBLIC OF NEW JERSEY My Commission expires on My Cci:i:u:i:i;.,5;0,1 Evpii*es March 24, rnaz
PROPOSED CHANGE TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 DESCRIPTION OF CHANGE
- Ref: LCR 84-12 Change the APPLICABILITY Section of Technical Specification 3.4.2.1 fo~ Unit No. 1, and 3.4.2 for Unit 2, Safety valves to read as follows:
"APPLICABILITY:
MODE.4 when the temperature of all RCS cold legs is greater than 312°F."
Remove the reference to the Overpressurization ProtectionSystem*
from the Safety Valve Te.chnical Specification* Bases for Unit
- No*. 2.
REASON FOR CHANGE The present specification wo*rding requires a pressurizer code safety valve to be operable in MODES.4 and 5.
In MODE 5 and in<
MODE 4 up to 312°F, the requirements of Technical Specification.
3.4.-9.3, Overpressure Protection Systems, provide adequate protection *for postulated overpressure conditions, i.e. most limiting h~at input and most limiting mass input transien~s.
The present specification, in addition to-being unnecessary for RCS ovepressurization protection for conditiohs not exceeding the proposed APPLICABILITY,.has brought about a del~y in the reassembly of the reactor vessel while the pressurizer code.
safeties are being calibrated off site.
The proposed change would eliminate *this constraint for future outages.
SIGNIFICANT HAZARDS EVALUATION Technical Specification 3.4.9.3 requires that an Overpressure Protection System shall be OPERABLE when the temperature of one or more of the RCS cold legs is less than or equal to 312°F, except when the vessel head is removed.
As stated in the Technical Specification Bases, the OPERABILITY of this system ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50.
Previously submitted analyses (References 1 -
5} of the most limiting heat input and mass input transients indicate that the RCS pressure will not exceed the Appendix G curve limit of 460 psig with RCS temperatures above 100°F when the Overpressure-
LCR 84-12 (continued}
Protection System is OPERABLE.
Based on the results of this analysis, we have determined that.the need does not exist for the OPERABILITY of a Pressurizer Code Safety Valve with a lift setting of 2485 psig + 1% when RCS.cold leg temperature is less than or equal to~°F. This analysis provides reasonable assurance that the operation of the Salem faciliti~s with the proposed change to the Technicial Specifications will neith~r involve a significant increase in the probability or consequence of any previously evaluated accident,.reduce a margin of safety, nor create the possibility for a new or different kind of accident.
The results of the change will remain within acceptable criteria*with 'respect to overpressure Protection Systems specified. in the Standard Review Plan.
This change conforms to example (VI} of Examples of Amendments That Are Considered Not Likely To Involve a Significant Hazards
- consideration as provided by the Commission in Federal Register 14870.
Refere*nces
- 1 PSEG (Librizzi} letter to NRC (Kniel} dated October 25, 1976 *.
- 2 PSEG (Librizzi}.* letter to NRC (Lear} dated March 25, 1977.
- 3 PSEG (Libri~zi) letter to NRC (Le~r}. dated May 3, 197J. *
- 4 PSEG (Librizzi} letter to NRC (Lear}' dated October 26, 1977.
- 5 "Pressure Mitigating System Transient Analysis Results" prepared by Westinghouse for the westinghouse*user's group on reactor coolant system overpressurization, dated July 1977.
.