ML18092A376
| ML18092A376 | |
| 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 | |
| ML18092A377 | List: |
| References | |
| LCR-84-11, NUDOCS 8411210019 | |
| Download: ML18092A376 (5) | |
Text
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r Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref:
LCR-84-11 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 3.4.1.2 regarding Reactor Coolant loops in operation while in MODE 3.
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.
8411210019 841015 PDR ADOCK 05000272 P
PDR The Energy People 95-21 68 (80 M) 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. Liden 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-84-11 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.
Subscribed and sworn to before me this /KJL day of~
, 1984 Notary Public of New Jersey DONNA G. HITCHNER NOT/\\RY PUBLIC OF NEW JERSEY My Commission expires on MyCommissionExpiresMarch24,1987
PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 DESCRIPTION OF CHANGE LCR 84-11
- 1)
Chang~ limiting condition for operation 3.4.l.2b to read as follows:
- b.
At least one of the above coolant loops shall be in operation* when the rod control system is de-energized**.
- 2)
Add limiting condition for operation 3.4.l.2C as follows:
- c.
At least two of the above coolant loops shall be in operation.when the rod control system is energized**
- 3)
Change the note with the single asterisk (*) to read as follows:
- All reactor coolant pumps may be de-energized.for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
(1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration (2) core outlet temperature is maintained at least 10°F below saturation temperature, and (3) the rod control system is de-energized**.
- 4)
Add the following note with a double asterisk (**):
- The rod control system shall be considered de-energized when.one or more of the following conditions exist:
- 1)
Both Rod Drive MG set motor breakers are open.
- 2)
Both Rod Drive MG set generator breakers are open.
- 3)
A combination of at least three of the Reactor Trip and/or Reactor Trip Bypass Breakers are open.
If none of the above condition for de-energizing the rod control system are met; the system shall be considered energized.
REASON FOR CHANGE:
It has been discovered that there is a potential unreviewed safety question concerning the consistency between the safety analysis and the Technical Specifications.
LCR 84-11 (continued)
According to 10CFR50.36, the assumptions in the safety analysis and the plant Tech Specs must be consistent.
This ensures that the plant is operated in a manner such that it is bounded by the FSAR accident analysis.
SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS This change constitutes an additional limitation, restriction, and control not presently included in the technical specifications, corresponding to Example (ii) of "Examples of Amendment That Are Considered Not Likely To Involve Significant Hazards Considerations" which were provided by the Commission in the Federal Register (48FR14870).
It has therefore been determined that this proposed change does not involve a Significant Hazards Consideration.