ML20207S037

Application for Amend to License NPF-57,revising Tech Spec 3.6.2.1 to Reflect Use of wide-range Instruments to Determine Suppression Chamber Water Inventory.Fee Paid

ML20207S037
Person / Time
Site:	Hope Creek
Issue date:	03/12/1987
From:	Corbin McNeil Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20207S038	List: ML20207S037 ML20207S044
References
NLR-N87023, NUDOCS 8703180456
Download: ML20207S037 (5)

Text

r Pubhc Service Electnc and Gas Company Corbin A. McNeill, Jr. Pubhc Service Electric and Gas Company P.O. Box 236. Hancocks Bndge, NJ 08038 609 339-4800

%ce President -

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March 12, 1987 NLR-N87023 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Dear Sir:

REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with the requirements of 10 CPR 50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS). In accordance with the requirements of 10 CFR 170.21, a check in the amount of $150.00 is enclosed. In accordance with the requirements of 10 CPR 50.91(b) (1), a copy of this request for amendment has been sent to the State of New Jersey as indicated below.

This change requests revision of Technical Specification 3.6.2.1 to correct an inaccuracy in the existing wording. Currently, the specifications state that narrow range suppression chamber water ,

level instruments are used to determine suppression chamber inventories. This shall be revised to correctly indicate the use of wide range instruments to determine the suppression chamber water inventory. This submittal includes three (3) signed originals, including affidavits, and forty (40) copies pursuant to 10 CPR 50.30(b) and (c).

Should you have any questions on the subject transmittal, please do not hesitate to contact us.

Sincerely,

_ A C N Enclosure (check)

Affidavit Attachments (2) o\

iI 0703180456 870312 PDR ADOCK 05000354 P PDR gy. e'c LUfC'IC 'I' flSO O

Document Control Desk 2 3/12/87 C Mr. D. H. Wagner NRC Licensing Project Manager Mr. R. W. Borchardt NRC Senior Resident Inspector Director, Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King ~of Prussia, PA 19406

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Ref: LCR 8 7-04 STATE OF NEW JERSEY )

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COUNTY OF SALEM )

Corbin A. McNeill, Jr., being duly sworn according to law deposes and says:

I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated March 12, 1987, concerning License Change Request 87-04 for Hope Creek Generating Station, is true to the best of my knowledge, information and belief.

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Subscribed and Sworn to before me this fj N, -day of h ,.1) , 1987 lOsj > da/l

' Notary Public of New Jersey A PetAsef Assy W hphesIlush M1900 My Commission expires on

r PROPOSED CHANGE TO Ref. LCR 87-04 TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION DESCRIPTION OF CHANGE Change the wording in Technical Specification 3.6.2.1, ACTION e) and f) from the present "... restore the narrow range suppression chamber water level..." to read,

"... restore the wide range suppression chanber water level...".

REASON FOR CHANGE This change is necessary to correct an inaccuracy in the existing specification. The wide range suppression chamber water level instruments, not narrow range indicators, are used to determine suppression chamber inventory during accident or transient conditions. The narrow range suppression chamber water level instrumentation is used only to initiate a transfer of the High Pressure Coolant Injection (HPCI) Pump suctions from the Condensate Storage Tank (CST) to the suppression chamber on a high water level in the suppression chamber. The narrow range suppression chamber function is covered in Technical Specifications Table 3.3.3-1.

SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS This change does not involve a significant increase in the probability or consequences of any previously evaluated accident or malfunction of equipment important to safety because the change is administrative in nature and constitutes a correction to the existing Technical Specification..

This proposed change does not create the possibility of a new or dif ferent kind of accident from any previously evaluated because there is no change to existing plant equipnent, procedures, or operating parameters. This change nakes an ACTION Statenent agree with original as-built design. Plant procedures have been written with due consideration of the error in this Technical Specification.

This proposed change does not involve a significant reduction in any nargin of safety. The change corrects an error in the existing Technical Specification that will ensure that the instrumentation of concern is properly addressed in the ACTION Statements.

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. Ref.'LCR 87-04 .

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, t, SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS ( Con t' d ) .r. .[ ~'

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Basedontheabove,we.havedeterminedthat'inibproposed change does not involve a Significant Hazards -r . -

Consideration. . Additionally, we suggest that'this change. ~ ~I conforms to example (i) of the guidance provided.by the Commission in 48FR14870.of the Federal Register f'or '

Amendments Not Likely To Involve A Significant Hazards Consideration, in that, the change is administrative'in ,

nature, making a correction to the existing Technical Specifications.  :;

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