IR 05000387/1997201
| ML17159A335 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/13/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17159A336 | List: |
| References | |
| 50-387-97-201, 50-388-97-201, NUDOCS 9805270118 | |
| Download: ML17159A335 (13) | |
Text
SUBJECT:
FIRE PROTECTION FUNCTIONALINSPECTION OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 (NRC INSPECTION REPORT NOS. 50-387/97-201 AND 50-388/97-201)
Dear Mr. Byram:
From October 20-24, and November 3-7, 1997, the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR), with technical inspection support from Brookhaven National Laboratories (BNL) and NRC Region I, performed a pilot fire protection functional inspection (FPFI) at the Susquehanna Steam Electric Station (SSES).
The FPFI evaluatedthe adequacy ofthe SSES fire protection program andits ability to: (1) prevent fires from starting, and (2) detect, control, suppress, and extinguish fires quickly; it also assessed the capabilities of the plant to achieve and maintain, post-fire safe-shutdown conditions using systems and components that have been protected and known to be free of fire damage.
'riaddition, this inspection evaluated the fire protection program's adherence to the design and licensing bases as established by Operating License NPF-14 (Unit 1), Condition 2.C(6) and NPF-22 (Unit 2), Condition 2.C(3); NRC safety evaluation reports; the SSES Final Safety Analysis Report (FSAR); the SSES Fire Protection Review Report (FPRR); and safe-shutdown analyses.
Within the areas inspected, the team examined procedures and records, interviewed plant operations and engineering support personnel, examined plant equipment and structures, and observed simulated responses to fire events.
The enclosed report presents the detailed scope and results of this inspection.
From the FPFI, the inspection team determined that the operational aspects (e.g., fire prevention program administrative controls) were satisfactory and appropriately implemented.
However, the team noted weaknesses associated with the design of certain plant fire protection features, fire brigade effectiveness, and certain aspects ofthe engineering analyses used to demonstrate that post-fire safe-shutdown conditions can be achieved and maintained.
Specifically, the team found sonic problems with the design of certain fire suppression and detection systems and their lack of conformance to industry fire protection standards; the fire brigade's ability to control and extinguish flammable/combustible liquid fires safely because of the plant policy to restrict the u~e of fire fighting foam on site; during an unannounced drill, the fire brigade was hindered by equipment logistics and deployment problems; the post-fire safe-shutdown methodology does not meet the Appendix R reactor performance goals by maintaining the reactor water level above the top of the active fuel or by assuring the availability 9805270ii8 'F805i3 PDR ADGCK 05000387
PDR III" B~'r em<ttEZ ee~r
Mr. Robert of keep-fill to prevent water hammer in the high-pressure core-injection system, reactor core isolation cooling system, core spray system, and residual heat removal system discharge piping; the preferred post-fire safe-shutdown instrumentation and required post-fire safe-shutdown manual actions were riot found in the procedures used for post-fire safe-shutdown from inside the control room; required emergency lighting was not provided in all plant areas in which post-fire safe-shutdown manual actions are taken, and a program that assures the operability of required emergency lighting in the "E" diesel building was not instituted; and the independent plant examination for external events (IPEEE) does not consider plant operational or fire conditions that could propagate into a large fire.
As with all NRC inspections, we expect that you willevaluate the applicability of the results and specific findings of this inspection to other systems, components and programs throughout the plant. You are requested to respond to the inspection report findings within 60 days from receipt of this letter.
In your response to the inspection findings, you should document any specific actions you have taken in response to the inspection. After reviewing your response to the inspection findings; the NRC willdetermine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure willbe placed in the NRC Public Document Room. Any enforcement action resulting from this inspection will be handled by NRC Region I staff and will be addressed by separate correspondence.
Should you have any questions concerning this inspection, please contact the project manager, Victor Nerses, at 301-415-1484, or the inspection team leader, Patrick M. Madden, at 301-415-2854.
Sincerely,
/s/
Robert A. Capra, Director Project Directorate Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket Nos.:
50-387 and 50-388 License Nos.:, NPF,-14 (Unit 1)
NPF-22 (Unit 2)
Enclosure:
NRC Inspection Report 50-387, 388/97-201 cc w/encl.: standard Susquehanna service list SEE DISTRIBUTION LIST ON NEXT PAGE DOCUMENT NAME: A:SUS TRAN.LTR * See previous concurrence
- SPLB:DSSA SPLB:DSSA
- SPLB:DSSA PMadden:rmc KSWest LBMarsh 04/10 /98 05/ 05/98 05/ 07 /98 PD:NRR RCapra +
05/i>/98 OFFICIAL RECORD COPY
t,
Mr. Robert. of keep-fill to prevent water hammer in the high-pressure core-injection system, reactor core isolation cooling system, core spray system, and residual heat removal system discharge piping; the preferred post-fire safe-shutdown instrumentation and required post-fire safe-shutdown manual actions were not found in the procedures used for post-fire safe-shutdown from inside the control room; required emergency lighting was not provided in all plant areas in which post-fire safe-shutdown manual actions are taken, and a program that assures the operability of required emergency lighting in the "E" diesel building was not instituted; and the independent plant examination for external events (IPEEE) does not consider plant operational or fire conditions that could propagate into a large fire.
Q As with all NRC inspections, we expect that you willevaluate the applicability of the results and specific findings of this inspection to other systems, components and programs throughout the plant. You are requested to respond to the inspection report findings within 60 days from receipt of this letter.
In your response to the inspection findings, you should document any specific actions you have takeri in response to the inspection. After reviewing your response to the inspection findings, the NRC willdetermine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure willbe placed in the NRC Public Document Room. Any enforcement action resulting from this inspection will be handled by NRC Region I staff and willbe addressed by separate correspondence.
Should you have any questions concerning this inspection, please contact the project manager, Victor Nerses, at 301-415-1484, or the inspection team leader, Patrick M. Madden, at 301-415-2854.
Sincerely, Robert A. Capra, Director Project Directorate Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket Nos.:
50-387 and 50-388 License Nos.: NPF-14 (Unit 1)
NPF-22 (Unit 2)
Enclosure:
NRC Inspection Report 50-387, 388/97-201 cc w/encl.: standard Susquehanna service list
I (
x
Mr. Robert TO PUBLIC Central Docket File (2)
CERossi, AEOD SPLB R/F Plant R/F Regional Administrators PIPB R/F Deputy Regional Administrators SPSB R/F EELB R/F ACRS (3)
BSheron OGC (3)
VNerses GHolahan SNewberry LMarsh KWest P Madden EConnell PQualls MSalley LWhitney WHRuland, RI ABelisle, Rll RGardner, Rill TStetka, RIV 3Zwolinski RCapr a
Mr. Robert Pennsylvania Power & Light Company Susquehanna Steam Electric Station, Units 1 8 2 CC.'ay Silberg, Esq.
Shaw, Pittman, Potts 8 Trowbridge 2300 N Street N.W.
Washington, D.C. 20037 'egional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 181 01 Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania I8I01 General Manager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1, Box 1797 Berwick, Pennsylvania 18603 Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O. Box 35 Berwick, Pennsylvania 18603-0035
'irector-Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. O. Box 8469 Harrisburg, Pennsylvania 17105-8469 George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803'r.
Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, Pennsylvania 17108-1266 Chairman Board of Supervisors
SUBJECT:
FIRE PROTECTION FUNCTIONALINSPECTION OF SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 (NRC INSPECTION REPORT NOS. 50-387/97-201 AND 50-388/97-201)
Dear Mr. Byram:
From October 20-24, and November 3-7, 1997, the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR), with technical inspection support from Brookhaven National Laboratories (BNL) and NRC Region I, performed a pilot fire protection functional inspection (FPFI) at the Susquehanna Steam Electric Station (SSES).
The FPFI evaluated the adequacy of the SSES fire protection program and its ability to: (1) prevent fires from starting, and (2) detect, control, suppress, and extinguish fires quickly; it also assessed the capabilities of the plant to achieve and maintain post-fire safe-shutdown conditions using systems and components that have been protected and known to be free of fire damage.
In addition, this inspection evaluated the fire protection program's adherence to the design and licensing bases as established by Operating License NPF-14 (Unit 1), Condition 2.C(6) and NPF-22 (Unit 2), Condition 2.C(3); NRC safety evaluation reports; the SSES Final Safety Analysis Report (FSAR); the SSES Fire Protection Review Report (FPRR); and safe-shutdown analyses.
Within the areas inspected, the team examined procedures and records, interviewed plant operations and engineering support personnel, examined plant equipment and structures, and observed simulated responses to fire events.
The enclosed report presents the detailed scope and results of this inspection.
From the FPFI, the inspection team determined that the operational aspects (e.g., fire prevention program administrative controls) were satisfactory and appropriately implemented.
However, the team noted weaknesses associated with the design of certain plant fire protection features, fire brigade effectiveness, and certain aspects of the engineering analyses used to demonstrate that post-fire safe-shutdown conditions can be achieved and maintained.
Specifically, the team found some problems with the design of certain fire suppression and detection systems and their lack of conformance to industry fire protection standards; the fire brigade's ability to control and extinguish flammable/combustible liquid fires safely because of the plant policy to restrict the use of fire fighting foam on site; during an unannounced drill, the fire brigade was hindered by equipment logistics and deployment problems; the post-fire safe-shutdown methodology does not meet the Appendix R reactor performance goals by maintaining the reactor water level above the top of the active fuel or by assuring the availability
Vq Mr. Robert of keep-fill to prevent water hammer in the high-pressure core-injection system, reactor core isolation cooling system, core spray system, and residual heat removal system discharge piping; the preferred post-fire safe-shutdown instrumentation and required post-fire safe-shutdown manual actions were not found in the procedures used for post-fire safe-shutdown from inside the control room; required emergency lighting was not provided in all plant areas in which post-fire safe-shutdown manual actions are taken, and a program that assures the operability of required emergency lighting in the "E" diesel building was not instituted; and the independent plant examination for external events (IPEEE) does not consider plant operational or fire conditions that could propagate into a large fire.
As with all NRC inspections, we expect that you willevaluate the applicability of the results and speciTic findings of this inspection to other systems, components and programs throughout the plant. You are requested to respond to the inspection report findings within 60 days from receipt of this letter.
In your response to the inspection findings, you should document any specific actions you have taken in response to the inspection. After reviewing your response to the inspection findings, the NRC willdetermine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room. Any enforcement action resulting from this inspection will be handled by NRC Region I staff and will be addressed by separate correspondence.
Should you have any questions concerning this inspection, please contact the project manager, Victor Nerses, at 301-415-1484, or the inspection team leader, Patrick M. Madden, at 301-415-2854.
Sincerely,
/s/
Robert A. Capra, Director Project Directorate Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket Nos.:
50-387 and 50-388 License Nos.: NPF-14 (Unit 1)
NPF-22 (Unit 2)
Enclosure:
NRC Inspection Report 50-387, 388/97-201 cc w/encl.: standard Susquehanna service list SEE DISTRIBUTIONLIST ON NEXT PAGE DOCUMENT NAME: A:SUS TRAN.LTR * See previous concurrence
- SPLB:DSSA SPLB:DSSA
- SPLB:DSSA PMadden:rmc KSWest LBMarsh 04/10 /98 05/ 05/98 05/ 07 /98 PD:NRR RCapra +
05/<~/98 OFFICIALRECORD COPY
Mr. Robert-of keep-fill to prevent water hammer in the high-pressure core-injection system, reactor core isolation cooling system, core spray system, and residual heat removal system discharge piping; the preferred post-fire safe-shutdown instrumentation and required post-fire safe-shutdown manual actions were not found in the procedures used for post-fire safe-shutdown from inside the control room; required emergency lighting was not provided in all plant areas in which post-flic safe-shutdown manual actions are taken, and a program that assures the operability of required emergency lighting in the "E" diesel building was not instituted; and the independent plant examination for external events (IPEEE) does not consider plant operational or fire conditions that could propagate into a large fire.
As with all NRC inspections, we expect that you willevaluate the applicability of the results and specific findings of this inspection to other systems, components and programs throughout the plant. You are requested to respond to the inspection report findings within 60 days from receipt of this letter.
In your response to the inspection findings, you should document any specific actions you have taken in response to the inspection. After reviewing your response to the inspection findings, the NRC willdetermine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room. Any enforcement action resulting from this inspection willbe handled by NRC Region I staff and willbe addressed by separate correspondence.
Should you have any questions concerning this inspection, please contact the project manager, Victor Nerses, at 301-415-1484, or the inspection team leader, Patrick M. Madden, at 301-415-2854.
Sincerely,
'obert A. Capra, Director Project Directorate Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket Nos.:
50-387 and 50-388 License Nos.: NPF-14 (Unit 1)
NPF-22 (Unit 2)
Enclosure:
NRC Inspection Report 50-387, 388/97-201 cc w/encl.: standard Susquehanna service list
PUBLIC Central Docket File (2)
CERossi, AEOD SPLB R/F
.
Plant R/F Regional Adminis PIPB R/F Deputy Regional SPSB R/F EELB R/F ACRS (3)
BSheron OGC (3)
VNerses GHolahan SNewberry LMarsh KWest PMadden EConnell PQualls MSalley LWhitney WHRuland, Rl ABelisle, Rll RGardner, Rill TStetka, RIV 3Zwolinski RCapra trators Administrators Mr. Robert DISTRIBUTION:
Mr. Robert Pennsylvania Power 8 Light Company Susquehanna Steam Electric Station, Units 1 8 2 CC:
Jay Silberg, Esq.
Shaw, Pittman, Potts 8 Trowbridge 2300 N Street N.W.
Washington, D.C. 20037 'egional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Bryan A. Snapp, Esq.
Assistant Corporate Counsel, Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania l8I01 Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O. Box 35 Berwick, Pennsylvania 18603-0035 Director-Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. O. Box 8469 Harrisburg, Pennsylvania 17105-8469 General Manager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 r
Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1, Box 1797 Berwick, Pennsylvania 18603
George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, Pennsylvania 17108-1266 Chairman Board of Supervisors 738 East Third Street Berwick, PA 18603