ML17165A019
| ML17165A019 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/30/1999 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| IEB-96-003, IEB-96-3, TAC-M96172, TAC-M96173, NUDOCS 9907070292 | |
| Download: ML17165A019 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Dune 30, 1999 Mr. Robert G. Byram Senior Vice President-Generation and Chief Nuclear Officer PP&L, Inc 2 North Ninth Street Allentown, PA 18101
SUBJECT:
COMPLETION OF LICENSING ACTION FOR BULLETIN96-03, "POTENTIAL PLUGGING OF EMERGENCY CORE COOLING SUCTION STRAINERS BY DEBRIS IN BOILING-WATERREACTORS," SUSQUEHANNA STEAM ELECTRIC STATION (SSES), UNITS 1 AND 2 (TAC NOS. M96172 AND M96173)
Dear Mr. Byram:
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 [BWRS]" to all holders of operating licenses or construction permits for boiling-water reactors.
The NRC issued BL 96-03 to ensure that the emergency core cooling systems (ECCS) in BWRs can perform their intended safety function to mitigate the effects of a postulated loss-of-coolant accident.
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 back flush 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 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 a letter dated October 4, 1996, as supplemented by letters dated November 5, 1996, April24, 1998, June 22, 1998, and March 12, 1999, for SSES, Units 1 and 2. You stated that you planned to install large capacity passive strainers that PPKL, Inc., would design using the guidance in the Boiling Water Reactors Owners Group UtilityResolution Guidance (URG). The staff reviewed the URG and issued a safety evaluation on August 20, 1998.
By letter dated May 27, 1999,'you informed the staff that you had completed all actions requested by the bulletin. These actions included adequately sizing the strainers to address the NRC Bulletin 96-03 concerns, installing the strainers in Units 1 and 2, carrying out the revised design basis for the ECCS strainers and updating the Final Safety Analysis Report in accordance with 10 CFR 50.71 requirements.
The staff has reviewed your response and has determined that the actions taken'should reduce the potential for clogging of ECCS suction strainers and ensure the capability of the ECCS to provide long-term cooling following a loss-of-coolant-accident as required by 10 CFR 50.46.
The staff notes that General Electric's Licensing Topical Report NEDC-32721P, "A'pplication Methodology for GE Stacked Disk Suction Strainer" is still undergoing staff review. Part I of the
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R. Byram staff's safety evaluation of the topical report was issued on February 3, 1999, approving GE's methodology for determining strainer head loss.
However, the GE methodology for calculating strainer and associated penetration structural loadings due to hydrodynamic forces is still under staff review. Part II of the staff's safety evaluation will be issued upon completion of this review.
Because the staff considers your actions responsive to the concerns raised in Bulletin 96-03 and no plant-specific concerns have been identified, BL 96-03 is closed for your facilities.
We may do detailed reviews of your strainer design and do a 10 CFR 50.59 evaluation on a plant-specific basis in the future.
If you have any questions regarding this matter, please contact me at (301) 415-1484.
Sincerely, Docket Nos. 50-387 and 50-388 cc: See next page Victor Nerses, Sr. Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation
t
Susquehanna Steam Electric Station, Units 1 82 Bryan A. Snapp, Esq.
Assoc. General Counsel PP8L, Inc.
2 North Ninth Street, GENTW3 Allentown, PA'181 01-1179 Terry L. Harpster Manager - Nuclear Licensing PP8L, Inc.
2 North Ninth Street, GENA61 Allentown, PA 18101-1179 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Director-Bureau of Radiation Protection Pennsylvania Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105-8469 Richard W. Osborne Allegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Robert F. Saunders Vice President-Nuclear Site Operations Susquehanna Steam Electric Station Box 467, NUCSA4 Berwick, PA 18603-0035 Mr. Herbert D. Woodeshick Special Office of the President PPBL, Inc.
Rural Route 1, Box 1797 Berwick, PA 18603-0035 George T. Jones Vice President-Nuclear Engineering & Support PPLL, Inc.
2 North Ninth Street, GENA61 Allentown, PA 18101-1179 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035
3une 30, 1999 R. Byram staff's safety evaluation of the topical report was issued on February 3, 1999, approving GE's methodology for determining strainer head loss.
However, the GE methodology for calculating strainer and associated penetration structural loadings due to hydrodynamic forces is still under staff review. Part li of the staff's safety evaluation willbe issued upon completion of this review.
Because the staff considers your actions responsive to the concerns raised in Bulletin 96-03 and no plant-specific concerns have been identified, BL 96-03 is closed for your facilities.
We may do detailed reviews of your strainer design and do a 10 CFR 50.59 evaluation on a piant-specific basis in the future.
Ifyou have any questions regarding this matter, please contact me at (301) 415-1484.
Sincerely, Original signed by:
Docket Nos. 50-387 and 50-388 cc: See next page Victor Nerses, Sr. Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation DISTRIBUTION:
Q)ocket-File~
PUBLiC PDI-1 Reading File S; Bajwa
~ E. Adensam (e-mail)
V. Nerses R. Elliot ACRS D. Skay C. Cowgill, RGN-I OGC J. Hannon DOCUMENT NAME: GAPDI-1ESusq1&2>BL96-03.wpd To receive a copy of this document, indicate
$ n the box:
"C" - Copy without attachment/enclosure "E"
Copy wIth attachment/enclosure "N" - No copy OFF ICE POI - I/PM VNe POI-2/LA MO'Brien SPLB/BC JMannon I-1/SC SBaJwa OATE 06
/99 06/
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0/99 OFFICIAL RECORD COPY
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(a dune 30, 1999 R. Byram staff's safety evaluation of the topical report was issued on February 3, 1999, approving GE's methodology for determining strainer head loss.
However, the GE methodology for calculating strainer and associated penetration structural loadings due to hydrodynamic forces is still under staff review. Part II of the staff's safety evaluation will be issued upon completion of this review.
Because the staff considers your actions responsive to.the concerns raised in Bulletin 96-03 and no plant-specific concerns have been identified, BL 96-03 is closed for your facilities.
We may do detailed reviews of your strainer design and do a 10 CFR 50.59 evaluation on a plant-specific basis in the future.
If you have any questions regarding this matter, please contact me at (301) 415-1484.
Sincerely, Original signed by:
Docket Nos. 50-387 and 50-388 cc: See next page Victor Nerses, Sr. Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation DISTRIBUTION:
Docket File PUBLIC PDI-1 Reading File S. Bajwa E. Adensam (e-mail)
V. Nerses R. Elliot ACRS D. Skay C. Cowgill, RGN-I OGC J. Hannon DOCUMENT NAME: GDPDI-1ESusq1&2EBL96-03.wpd To receive a copy of this document, indicate in the box:
"C" - Copy without attachment/enclosure "E"
Copy with attachment/enclosure "N" - No copy OFFICE POI-I/PN POI-2/LA SPLB/BC I-1/sc DATE VNe 06
/99 NO'Brien 06/ I i/99 JHannon 06/
9 SBajwa 06/
0/99 OFFICIAL RECORD COPY
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