ML20207A345
| ML20207A345 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/20/1999 |
| From: | Richard Ennis NRC (Affiliation Not Assigned) |
| To: | Keiser H Public Service Enterprise Group |
| References | |
| IEB-96-003, IEB-96-3, TAC-M96150, NUDOCS 9905260276 | |
| Download: ML20207A345 (4) | |
Text
-
(
g*
4 UNITED STATES i
g 9j NUCLEAR REGULATORY COMMISSION
~t WASHINGTON. D.C. 20666-0001 May 20, 1999
{
i Mr. Harold W. Keiser Chief Nuclear Officer & President -
Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038 j
SUBJECT:
COMPLETION OF LICENSING ACTION FOR NRC BULLETIN 96-03,
' POTENTIAL PLUGGING OF EMERGENCY CORE COOLING SUCTION STRAINERS BY DEBRIS IN BOILING-WATER REACTORS," HOPE CREEK GENERATING STATION (TAC NO. M96150)
Dear Mr. Keiser:
On May 6,1996, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin (BL) 96-03,
" Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors," to all holders of operating lice'nses or construction permits for boiling-water reactors (BWRs). The NRC issued BL 96-03 to ensure that the emergency core cooling systems I
(ECCS)in BWRs can perform their intended safety function to mitigate the effects of a postulated loss-of-coolant accident (LOCA). The BL provided three options for resolving this issue including (1) installation of large capacity passive strainers, (2) installation of self-cleaning strainers, or (3) installation of a backflush system.
In BL 96-03, the NRC staff specifically requested that licensees submit the following reports for each of their facilities:
1.
A description of planned actions and mitigative strategies to be used, the schedule for implementation, and proposed technical specification, if appropriate.
2.
A report confirming completion and summarizing actions taken.
In response to BL 96-03, you provided letters dated November 4,1996, May 20,1997, July 18, 1997, and September 26,1997 for Hope Creek Generating Station (HCGS). Your letters stated that you planned to install large capacity straincts on the core spray and residual heat removal pump suction lines and that the methods described in the Bolling Water Reactors Owners Group Utility Resolution Guidance (URG) would serve as the basis for sizing the strainers. The letter dated May 20,1997, requested the NRC staff to perform a plant specific review in order
'{}
to approve the proposed BL 96-03 resolution approach for HCGS prior to strainer installation.
The plant-specific review was requested since the NRC review of the URG was not complete at i
that time. In a safety evaluation dated October 31,1997, the staff concluded that your sizing criteria for your proposed new strainer design for HCGS was adequate provided that you performed an analysis which demonstrates that the non-credible breaks which you originally
/
screened out of your plant-specific evaluation would not be more limiting in terms of head loss \\)\\
than the breaks included in your initial analysis. In a [[letter::LR-N980313, Provides Updated Info for Issues Discussed in NRC 961104, 970520 & 0718 SERs of Licensee Response to NRC Bulletin 96-003, Potential Plugging of ECCS Suction Strainers by Debris|letter dated June 25,1998]], you provided
(/
updated information to address the issues discussed in the safety evaluation. Subsequently, the staff completed the review of the URG and issued a safety evaluation on A s
h hk 7
9905260276 990520 PDR ADOCK 05000354 G
PM g
r
,[
?'
H. Keiser By letter dated April 27,1999, you informed the staff that you had completed all actions requested by the bulletin. Your letter stated that installation of the large capacity strainers was completed during the HCGS refueling outage which ended on March 31,1999. The letter also stated that inspections performed during drywell and suppression pool closeout, in combination with foreign material control would provide adequate administrative controls for ECCS pump suction strainer operability. In addition, the letter stated that suppression pool cleaning will continue to be performed at a frequency to ensure that the assumed debris loadings for the strainers are not exceeded.
{
The staff has reviewed your response and has determined that the actions taken should minimize the potential for clogging of ECCS suction strainers and ensure the capability of the i
ECCS to provide long-term cooling following a LOCA as required by 10 CFR 50.46. The staff considers your actions responsive to the concerns raised in BL 96-03. Therefore, BL 96-03 is closed for HCGS. Detailed reviews of your strainer design and 10 CFR 50.59 evaluation may be performed on a plant-specific basis in the future.
If you have any questions regarding this matter, please contact me at (301) 415-1420.
Sincerely,
)
Richard B. Ennis, Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354 cc: See next page
5 Tk H. Keiser May 20, 1999 By letter dated April 27,1999, you informed the staff that you had completed all actions requested by the bulletm. Your letter stated that installation of the large capacity strainers was completed during the HCGS refueling outage which ended on March 31,1999. The letter also stated that inspechons performed during drywell and suppression pool closeout, in combination with foreign material control would provide adequate administrative controls for ECCS pump suction stramer operability, in addition, the letter stated that suppression pool cleaning will continue to be performed at a frequency to ensure that the assumed debris loadegs for the strainers are not exceeded.
The staff has reviewed your response and has determined that the actions taken should minimize the potential for clogging of ECCS suction strainers and ensure the capability of the ECCS to provide long-term cooling following a LOCA as required by 10 CFR 50.46. The staff considers your actions responsive to the concems raised in BL 96-03. Therefore, BL 96-03 is closed for HCGS. Detailed reviews of your strainer design and 10 CFR 50.59 evaluation may be performed on a plant specific basis in the future.
If you have any questions regarding this matter, please contact me at (301) 415-1420.
Sincerely, ORIGINAL SIGNED BY:
Richard B. Ennis, Project Manager, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No.' 50-354 cc: See next page DISTRIBUTION Decket File JClifford RElliot GMeyer, RI PUBLIC -
MO'Brien JHannon PDl-2 R/F REnnis OGC SBlack DSkay
.ACRS DOCUMENT NAME: LTR96150.WPD
%e(Ado OFFICE PDI-2/PM PDinlibMV SPLB/BC PDI-2/SC NAME REnnis h '
MOSrib JClifhd JHann 1-hM /99 DATE
[/R/99 h/ h/99
[/
/99 l
OFFICIAL RECOR'D COPY i
q Hope Creek Generating Station cc:
Jeffrie J. Keenan, Esquire Manager-Joint Generation Nuclear Business Unit-N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bridge, NJ 08038 Egg Harbor Twp., NJ 08234-4130 Hope Creek Resident inspector Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation Drawer 050g Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Creek Township Nuclear Department c/o Mary O. Henderson, Clerk P.O. Box 236
- J. ^' cal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancot is Bridge, NJ 08038 General Manager-Hope Creek Operations Mr. Elbert Simpson Hope Creek Generating Station Senior Vice President-P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ 08038 Nuclear Department P.O. Box 236 Director-Licensing Regulation & Fuels Hancocks Bridge, NJ 08038 Nuclear Business Unit-N21 P.O. Box 236 Hr.acocks Bridge, NJ 08038 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 J