ML18094B123
| ML18094B123 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/17/1989 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18094B124 | List: |
| References | |
| NLR-N89190, NUDOCS 8910200224 | |
| Download: ML18094B123 (6) | |
Text
Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer October 17, 1989 NLR-N89190 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
REQUEST FOR AMENDMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating station (SGS), Unit Nos. 1 and 2.
Pursuant to the requirements of 10CFR50.90(b) (1), a copy of this request has been sent to the State of New Jersey as indicated below.
The proposed change requests a modification to the 125 and 28 volt battery capacity Technical Specification surveillance requirements.
The change eliminates the discrepancy that presently exists between the method used to test station batteries and the description/design criteria specified in the UFSAR.
PSE&G would like to implement this change for the next Unit 2 refueling outage, presently scheduled for 3/31/90, although it is not imperative.
The proposed changes are requested to obtain similarity between the Technical Specifications and UFSAR.
The revisions proposed herein are consistent with NRC regulations and guidance (e.g.
Regulatory Guide 1.129) and Westinghouse Standard Technical Specifications.
Therefore, a significant amount of technical review should not be required.
PSE&G believes that the proposed change can be classified as a Category 2 change. contains further discussion and justification for the proposed revisions. is a markup of the existing Technical Specifications to reflect the specifications as requested. is a retype of the Technical Specifications incorporating the proposed changes.
contains information describing the criteria and methodology utilized to identify and calculate the battery loads, to be used for the load profile service tests.
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fDR ADOCK 05000272
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Document Control Desk NLR-N89190 2
10-17-89 This submittal includes one (1) signed original, including affidavit, and thirty-seven (37) copies pursuant to 10CFR50.4 (b)
(2) (ii).
Should you have any questions on this subject transmittal, please do not hesitate to contact us.
Sincerely, Attachments
~£~
c Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. W. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
REF:
NLR-N89190 STATE OF NEW JERSEY SS.
COUNTY OF SALEM
- s. Miltenberger, being duly sworn according to law deposes and says:
I am Vice President and Chief Nuclear Officer of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated October 17, 1989
, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
- Subscribed and Sworn to before me this *. 11-fic day of tPc/otf?t 1989
- ,iJ£A:,,ifL ~ *~
Nota:r:y Public of New Jersey V.5.NlH* !:~. WHlS!iALL MOTmW PU3UG Cf NEW JERSEY f\\~J Conrn1lssl~~1 E:;;::lrns M;JV 6, 1993 My Commission expires on ~~~~~~~~~~~~~~~-
PROPOSED LICENSE CHANGE SALEM GENERATING STATION UNIT NOS. 1 AND 2 ATTACHMENT 1 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 I.
Description of the Change LCR 89-07 Revise Salem Unit 1 and 2 Technical Specification Surveillance Sections 4.8.2.3.2 (d) and 4.8.2.5.2 (d) *to require a design duty cycle load profile service test (simulated emergency loads) or load service test (actual loads) in lieu of the (8) hour load service test currently specified in the Technical Specifications.
II.
Reason for the Proposed Change The proposed change revises the battery capacity service test surveillances to be consistent with the Salem Generating Station UFSAR and Westinghouse Standard Technical Specifications.
UFSAR section 8.3.2.2 describes battery design capacity as follows:
"The batteries are sized for (2) hours of operation after a loss of AC power, based upon the required operation of the DC emergency equipment".
The present Technical Specification Surveillance requires an (8) hour battery capacity service test.
The present Technical Specification Surveillance also requires a load service test utilizing actual loads.
The proposed change allows the option of conducting a load profile service test (simulated emergency loads) or a load service test (actual loads).
This change provides flexibility for satisfying the surveillance requirements.
III. Justification for the Proposed Change PSE&G complies with Regulatory Guide 1.129, which endorses IEEE STD-450.
IEEE STD-450 describes a recommended procedure for conducting battery service tests.
The recommended procedure states in part, "The discharge rate and length should correspond as closely as is practical to the design requirements (battery duty cycle) of the DC system".
The proposed change satisfies this requirement by bringing the battery service test in-line with the design requirements.
Conducting (8) hour battery capacity service tests does not ensure that the battery is capable of sustaining the DC emergency equipment for the design duty cycle.
The (8) hour test utilizes lower discharge current rates than those experienced at the design duty cycle test length.
In addition, the battery manufacturer has recommended battery testing at the design duty cycle rate.
The use of simulated emergency loads in lieu of actual loads is consistent
with the Westinghouse Standard Technical Specifications Revision 4, previously reviewed and approved by the NRC and other nuclear facilities (Calvert Cliffs, Turkey Point, Zion).
The load profile service test will be conducted for the design duty cycle duration at the loading values specified within the surveillance procedure.
The actual loading values are established based on battery loading calculations.
The Technical Specification Surveillance frequency is unaffected by this modification.
The reduction in battery service test duration from (8) hours to the design duty cycle and the use of simulated emergency loads achieves consistency between the Salem Generating Station Technical Specifications, Salem Generating Station UFSAR and Westinghouse Standard Technical Specifications.
IV.
Significant Hazards Analysis Consideration The proposed changes to the Technical Specifications:
- 1.
Do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes ensure that the battery surveillance acceptance criteria is based on the battery design duty cycle.
An accurate determination of battery capacity, based on design duty cycle, provides assurance that the batteries will fulfill their design function when required.
Therefore, it may be concluded that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2.
Do not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes do not adversely affect the design or operation of any system or component important to safety.
No physical plant modifications or new operational configurations will result from these changes.
Therefore, it may be concluded that the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3.
Do not involve a significant reduction in a margin of safety.
The margin of safety is maintained, since satisfactory surveillance results will clearly indicate acceptable battery capacity.
The proposed change achieves consistency between the surveillance requirements and the component design and does not affect the surveillance frequency.
The change does not make any physical alterations to the plant and is consistent with the previously reviewed and approved Westinghouse Standard Technical Specifications.
Therefore, it may be concluded that the proposed changes do not involve a significant reduction in a margin of safety.
IV.
Conclusions Based on the information presented above, PSE&G has concluded that the proposed changes satisfy the criteria for a no significant hazards consideration.