ML20154H486
| ML20154H486 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/16/1988 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| IEB-88-007, IEB-88-7, NLR-N88151, NUDOCS 8809220020 | |
| Download: ML20154H486 (4) | |
Text
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Pubhc Service Electnc and Gas Company Steven E. Miltenberge, PubHc Service E!cctric and Gas Company P.O. Box 236. Hancocks Bndge. NJ 08038 609-339-4199 V(e bes4 eat a^d Ch e' Ncw ONer September 16, 1988 NLR-N88151 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlement RESPONSE TO NRC BULLETIN NO. 88-07 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Public Service Electric and Gas Complany (PSE&G) has complied with the requirements of NRC Bulletin No. 88-07, "Power Oscillations in Boiling Water Reactors".
We have determined, based upon our reviews as described in Attachment 1, that our crerating procedures, training programs and installed instrumentation cy?' ems aco adequate for the use of operating personnel for the preventJon, recognition, control and termination of power oscillations at the Hope Croek Generating Station.
We will be pleased to discuss any questions you may have regaraing this transmittal.
Sincerely, b&
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Mr. William T.
Russell, Administrator 1
USNRC Region I
$o Mr.
G.
W. Rivenbark USNRC Licensing Project Manager og cua 88 Mr.
G.
W.
Meyer Q4 USNRC Senior Resident Inspector s
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Acting Chiof (O A O Bureau of Nuclear Engineering NJ Department of Environmental Protection
{gg 380 Scotch Road l
Trenton, NJ 08628 g
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3-Reft BULLETIN 88-07 STATE OF NEW JERSEY
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SS.
COUNTY OF SALEM
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i Steven E. 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 concerning Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, are true to the best of my knowledge, information and belief.
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Subscribep and Sworn Ao before mo this /4,M day of J, M,,/#c, 1988 i
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b4 SE0ms D.HA0058 Notary Public of New Jersey g
gmg Idy heira Mme K1800 My Commission, expires on i
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f ATTACHMENT 1 IE BULLETIN 88-07 "Power Oscillations in Boiling Water Reactors" In response to the subject Bulletin, PSE&G submits the following for the Hope Creek Generating Station:
1)
All licensed reactor operators and Shift Technical Advisors performing shift duties were thoroughly briefed regarding the March 9, 1988 LaSalle Unit 2 event within 15 days of receipt of the subject Bulletin.
2)
Within 60 days of receipt of the bulletin, PSE&G completed an adequacy review of all procedures and training programs associated with the prevention, recognition, control and termination of uncontrolled power oscillations.
Based on the significance of the LaSalle Unit 2 event, PSE&G implemented temporary operating restrictions for the Hope Creek plant prior to beginning the above reviews.
These restrictions included immediate power reductions following recirc pump trips and runbacks, and reactor scram on APRM power oscillations of greater than 10% power peak-to-peak.
Additionally, restart of recirc pumps was prohibited above the 80% rod line.
The review of the Hope Creek operating procedures identified various areas that could benefit from recommendations in Reference 1.
These procedural enhancements have been completed.
Accordingly, our operator training programs, which train to approved procedures, will reflect these improvements.
The first cycle of operatoe training that will include a review of these revised procedures commenced on September 6, 1988.
It should be noted that precautions against reactor core power instabilities were already incorporated in our operating procedures and training programs prior to the LaSalle Unit 2 event; the latest procedural revisions merely reenforce that information of which the operators were already aware.
3)
Our procedures and operator training programs require, as recommended in Reference 1, that the operators monitor the APRMs and LPRMs for normal and abnormal flux variations.
These instruments, which are used for core stability determinations, are part of the standard General Electric Company (GE) Neutron Monitoring System (NMS).
The GE NMS was reviewed for adequacy during the NRC resolution of Generic Issuo B-19.
This instrumentation was approved by the NRC as an effective means of detecting instabilities (References 2 and 3).
There have been no modifications of the GE NMS at Hope Creek Generating Station that could affect this ability.
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( Attachment 1 - Cont'd) 2 The NRC Augmented Inspection Team investigating the LaSalle event (Reference 4) presented several adequacy concerns with regard to APRM/LPRM instruments each of which have been assessed at HCGS.
Based on of the NRC's assessment of the adequacy of the APRMs and LPRMs and on the results our review of the equipment installed at our facility, we have determined that our instrumentation is adequate for reactor core stability determinations.
REFERENCES:
1.
General Electric Company Service Information Letter No. 380, Revision 1, "BWR Core Thermal Hydraulic Stability", February 10, 1984.
2.
- Letter, C.O. Thomas (NRC) to H.C.Pfefferlen (GE), "Acceptance for Referencing of Licensing Topical Report NEDE-240ll, Rev.
6, Amendment 8,
' Thermal Hydraulic Stability Amendment to GESTAR II'
, April 24, 1985.
3.
Letter, R.M.Bernero (NRC) to All Licensees of Oparating BWRs, "Technical Rosolution of Generic Issue B Thermal Hydr:aulic Stability (Generic Letter No. 0 6-02)", January 23, 1986.
4.
Latter, E.G.Greenman ( NRC) to C. Reed (CECO), Docket No.
50-373 and 50-374, Transmittal of Augmented Inspection Team Report, May 16, 1988.
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