ML20237F137
| ML20237F137 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/25/1998 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LCR-H98-03, LCR-H98-3, LR-N98407, NUDOCS 9809020084 | |
| Download: ML20237F137 (6) | |
Text
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a Pubhc Servce Electrc and Gas company E. C. simpson Put>he Service Electnc and Gas Cornpany P O. Box 236. Hancocks Bridge. NJ 08038 609-339-1700 semor Vme heujont - Nuoear E ngenoenrg g
LR-N98407 LCR H98-03 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENT TO A REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS DELETION OF AUTOMATIC DEPRESSURIZATION SYSTEM VALVE STARTUP TESTING HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 On June 25,1998, via letter LR-N08277, Public Cervice Electric & Gas (PSE&G)
Company transmitted License Change Request (LCR) H98-03 to the NRC to request a revision to the Technical Specifications (TS) for the Hope Creek Generating Station.
Specifically, LCR H98-03 requested, in part, a deletion of the requirement to perform in-situ functional testing of the Automatic Depressurization System (ADS) valves once every 18 months as part of stadup testing activities. On August 6,1998, PSE&G held a teleconference with NRC representatives reviewing the LCR submittal. As a result of the teleconference, the NRC has asked additional questions concerning the proposed acoustic monitor channel calibration methodology. The information PSE&G provided in
/
response to this question is attached to this letter, which being provided to facilitate the
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NRC's review of the LCR submittal.
PSE&G has determined that the information contained in the attachment to this letter does not alter the conclusions reached in the 10CFR50.92 No Significant Hazards analysis previously submitted with LCR H98-03. In accordance with 10CFR50.91(b)(1), //&/
a copy of this submittal has been sent to the State of New Jersey. Should you have any questions regarding this request, please contact James Priest at 609-339-5434.
Sincerely,
/
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Affidavit Attachment 9009020004 980825 T
PDR ADOCK 0500o354 P
PDR l
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AUGas ses Document Control Desk. LR-N,98407 C
Mr. H. Miller, Administrator - Region i U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 14E21 11555 Rockville Pike Rockville, MD 20852 Mr. S. Pindale (X24)
I USNRC Senior Resident inspector-HC
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Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 I
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95-4933
REF: LR-N98407 LCR H98-03 STATE OF NEW JERSEY )
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COUNTY OF SALEM
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E. C. Simpson, being duly sworn according to law deposes and says:
I am Senior Vice President - Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Hope Creek Generating Station, Unit 1, are true to the best of my knowledge, information and belief.
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r Subscribed and Sworn to before me day of 1, u_,n a61998 this d 5 M
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ATTACHMENT HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 SUPPLEMENTAL INFORMATION The following information provides additional details concerning the method of acoustic monitor channel calibration:
Outline of proposed MSRV Acoustic monitoring alternate testing.
l Point B l Point A To Control Acoustic M nRor To junction Room box outside drywell.
MSRV discharge line.
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I To Torus Test methodology:
- 1. Channel calibration is performed on system from (point "A")
junction box outside of drywell to control room cabinet (point "B").
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- 2. The acoustic monitor is removed from the attachment strap by disconnecting the Namco connector and unscrewing the accelerometer from the pipe attachment strap.
The accelerometer is screwed onto the portable shaker (PCB Piezotronics model 394C06) or equivalent (See attached information).
- 3. The handheld shaker is started and the accelerometer produces an l
output to the control room cabinet.
l
- 4. The output is scaled up to previous levels (until indication occurs).
- 5. After indication verification, the setpoint is established based upon previous cycle calibration levels or as required to establish an appropriate alarm response.
- 6. Failure of the sensor is indicated by an excessively high scaling factor required for an alarm response.
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