ML17158A815
| ML17158A815 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/09/1995 |
| From: | Poslusny C NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| TAC-M91323, NUDOCS 9508150056 | |
| Download: ML17158A815 (6) | |
Text
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+ 9, 1995 Hr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101
SUBJECT:
REQUEST FOR INFORMATION REGARDING REACTOR WATER CLEANUP SYSTEM SUBCOHPARTHENT ANALYSIS (TAC NO. H91323)
Dear Hr. Byram:
During the review of the Advanced Boiling Water Reactor, the Advisory Committee on Reactor Safeguards raised an issue on the potential for an unisolable break in the reactor water cleanup (RWCU) system and requested that the staff consider the issue for operating Boiling Water Reactor plants.
The Office of Nuclear Reactor Regulation staff is following-up on some questions related to this issue involving the environmental effects of a postulated RWCU system break within secondary containment.
The staff is reviewing final safety analysis report (FSAR) design information for several plants with different containment design and is conducting independent code analyses to address the ACRS concerns.
Currently the staff is reviewing Susquehanna Steam Electric Station (SSES) information.
In a recent phone call with your staff, we discussed the information we have reviewed in the SSES FSAR and have identified some additional information not included in the FSAR which would support the staff's independent analysis.
Your staff indicated that it could provide the information with minimal impact on staff resources.
Please submit your response to the enclosed request on the docket.
We appreciate your support of-this staff study and will keep your staff informed of findings.
This requirement affects 9 or fewer respondents and, therefore, is not subject to the Office'f Management and Budget review under P.L.96-511.
9508iSOOse 9SOS09 g PDR ADQCK OS000387 P
PDRi Docket Nos.
50-387/388
Enclosure:
RAI Sincerely, Original signed by Chester, Poslusny, Senior Project Manager Project Directorate I-2
'ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/encl:
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Hr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 9, 1995
SUBJECT:
REQUEST FOR INFORMATION REGARDING REACTOR WATER CLEANUP SYSTEM SUBCOMPARTHENT ANALYSIS (TAC NO. H91323)
Dear Hr. Byram:
In a recent phone call with your staff, we discussed the information we have reviewed in the SSES FSAR and have identified some additional information not included in the FSAR which would support the staff's independent analysis.
Your staff indicated that it could provide the information with minimal impact on staff resources.
During the review of the Advanced Boiling Water Reactor, the Advisory Committee on Reactor Safeguards raised an issue on the potential for an unisolable break in the reactor water cleanup (RWCU) system and requested that the staff consider the issue for operating Boiling Water Reactor plants.
The Office of Nuclear Reactor Regulation staff is following-up on some questions related to this issue involving the environmental effects of a postulated RWCU system break within secondary containment.
The staff is reviewing final safety analysis report (FSAR) design information for several plants with different containment design and is conducting independent code analyses to address the ACRS concerns.
Currently the staff is reviewing Susquehanna Steam Electric Station (SSES) information.
Please submit your response to the enclosed request on the docket.
We appreciate your support of this staff study and will keep your staff informed of findings.
This requirement affects 9 or fewer respondents and, therefore, is not subject to the Office of Management and Budget review under P.L.96-511.
Sincerely, Docket Nos.
50-387/388
Enclosure:
RAI cc w/encl:
See next page Chester
- Poslusny, Senior Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Hr. Robert G.
Byram Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units 1
& 2 CC:
Jay Silberg, Esq.
'haw,
- Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street
'llentown, Pennsylvania 18101 Hr. J.
H. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hrs. Haitri Banerjee Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Hr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Hr. 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 Hr. Harold G. Stanley Vice President-Nuclear Operations Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Hr. 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 Engineering 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
P
REQUEST FOR ADDITIONAL INFORMATION FOR RWCU SYSTEM ANALYSIS Provide the NRC-staff with the following information to permit us to independently audit the subcompartment pressures and temperatures that might
'esult from a postulated double-ended break of the RWCU piping inside secondary containment.
Please provide the information in SI units if available.
of time.
1.
Mass flow rate and enthalphy release tables from the break as a funct' a
unc ion 2.
For the affected room and adjacent
- rooms, provide the volume, height, and relative elevation for each room.
3.
For the doors and vents between the rooms provide the flow path areas, equivalent lengths, and loss coefficients.
4.
For swinging doors and blowout panels, provide the differential pressure required for opening.
4
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