ML17159A065
| ML17159A065 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/25/1997 |
| From: | Poslusny C NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| TAC-M96307, TAC-M96308, NUDOCS 9712030238 | |
| Download: ML17159A065 (9) | |
Text
'1 Novemher 25, 19~
'Nr. Robert G.
Byram Senior Vice President-Generation and,Chief Nuclear Officer Pennsylvania Power and Light
. Company
- , 2 North. Ninth Street Allentown, PA 18101
SUBJECT:
CHANGES TO THE BASES OF THE TECHNICAL SPECIFICATIONS, SUSQUEHANNA STEAN ELECTRIC STATION, UNITS 1
AND 2 (TAC NOS.
H96307 AND N96308),'ear Hr. Byram:
By letter dated March 12,
- 1996, Pennsylvania Power and Light Company ll submitted changes to the Bases of the Susquehanna Steam Electric Station, Units 1
and 2 Technical Specifications (TSs).
These changes revise existing Bases Section 3/4.3.7.5 to reflect the use of the Neutron Monitoring System for post-accident monitoring.
This letter acknowledges these changes to the TS Bases section.
TS Page B 3/4 3-5 for each unit with the proposed changes are enclosed.
Sincerely,
/s/
Chester
- Poslusny, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos.
50-387 and 50-388
Enclosure:
As stated cc w/encl:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 November 25, 1997 Hr. Robert G.
Byram Senior Vice President-Generation and Chief Nuclear Officer Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101
SUBJECT:
CHANGES TO THE BASES OF THE TECHNICAL SPECIFICATIONS, SUSQUEHANNA
'TEAN ELECTRIC STATION, UNITS 1
AND 2 (TAC NOS.
H96307 AND H96308)
Dear Hr. Byram:
By letter dated Harch 12,
- 1996, Pennsylvania Power and Light Company submitted changes to the Bases of the Susquehanna Steam Electric Station, Units 1 and 2 Technical Specifications (TSs).
These changes revise existing Bases Section 3/4.3.7.5 to reflect the use of the Neutron Honitoring System for post-accident monitoring.
This letter, acknowledges these changes to the TS Bases section.
TS Page B 3/4 3-5 for each unit with the proposed changes are enclosed.
Sincerely, Docket Nos. 50-387 and 50-388
Enclosure:
As stated cc w/encl:
See next page Chester
- Poslusny, Senior Project Hanager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Mr. Robert G.
Byram Pennsylvania Power 5 Light Company Susquehanna Steam Electric Station, Units 1 5 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts E Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 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. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 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 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 Chairman Board of Supervisors 738 East Third Street
- Berwick, PA 18603
C
BASES The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February, 1972.
The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations".
The Neutron Monitoring System (NMS) was evaluated against the criteria established in General Electric NEDO-31558A to ensure its acceptability for post-accident monitoring.
NEDO-31558A provides alternative criteria for the NMS to meet the post-accident monitoring guidance of Regulatory Guide 1.97.
Based on the evaluation, the NMS was found to meet the criteria established in NEDO-31558A. The APRM sub-function of the NMS is used to provide the Neutron Flux monitoring identified in TS 3.3.7.5.
The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
The OPERABILITYof the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.
SUSQUEHANNA - UNIT 1 B 3/4 3-5 Amendment No.
BASES The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February, 1972.
The OPERABILITYof the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is.
available 'on selected plant parameters to monitor and assess important variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"
December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations".
The Neutron Monitoring System (NMS) was evaluated against the criteria established in General Electric NEDO-31558A to ensure its acceptability for post-accident monitoring.
NEDO-31558A provides alternative criteria for the NMS to meet the post-accident monitoring guidance of Regulatory Guide 1.97.
Based on the evaluation, the NMS was found to meet the criteria established in NEDO-31558A.
The APRM sub-function of the NMS is used to provide the Neutron Flux monitoring identified in TS 3.3.7.5.
The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown.
At these power levels, reactivity additions should not be made without this flux level information available to the operator.
When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.
SUSQUEHANNA - UNIT 2 B 3/4 3-5 Amendment No.
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