ML17138B301
| ML17138B301 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 04/07/1980 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8005130742 | |
| Download: ML17138B301 (6) | |
Text
Docket Nos. 50-387/
88
Dear Mr. Curtis:
DISTRIBUTION APR 0'7 (QBp Docket File NRC PDR Local PDR LWR ¹3 File D.
Ross D. Vassallo S. Varga ter.
Norman W. Curtis F. Williams Vice President - Engineering 0
Pa<<
and Construction R. Stark Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 e closaC3f:
M.
ushbrook R. Mattson S.
Hanauer J. Knight R. Tedesco R.
DeYoung BCC:
ACRS (16)
V. Moore NSIC W. Kreger TIC M. Ernst R. Denise OELD IE (3)
T.
II1ur phy P. Collins J. Ninns
SUBJECT:
SUStlUEHANNA STEAM ELECTRIC STATIOt), UNITS NOS.
1 5 2-REQUEST FOR ADDITIOINAL INFORtQTION As a result of our continuing review of the FSAR through Amendment No. 20 for Susquehanna Units 1
9 2, the Radiation Protection Section has developed the enclosed positions and requests for additional information.
The specific information required is listed in the Enclosure.
Please contact us if you desire any discussion or clarification of the information requested.
Sincerely, ctad~I. I +
~
~ ~~d 0.
Olan D. Parr, Chief Light ':later Reactors Branch No.
3 Division of Project I'tanagement
Enclosure:
Request for Additional Information cc w/enclosure:
See next page p()dy) p 0 7I~
OFFICE $
SURNAME OATE $
L'8'PM'"
RStark/LLN 4/
/80 4/ 7
/80 NRC FORM 316 (9'i6) NRC. I 32'0
~ U.S. GOVERNMENT PRINTING OFFICE: 1979'269 369
C
~o
Mr. Norman W. Curtis APR O '/ )980 cc:
Mr. Earle M. Mead Project Engineering Manager Pennsylvania Power
& Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani a 18101 Jay Silberg, Esq.
- Shaw, Pi ttman, Potts Trowbridge 1800 M Street, N.
W.
. Washington, D. C.
20036 Mr. William E. Barberich, Nuclear Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Al 1 ento>rn, Pennsyl vania 18101 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsyl vani a 18101 Bryan Snapp, Esq.
Pennsylvania Power
& Light Company 901 Hamilton Street Al 1entown, Pennsyl vania 18101 Robert M. Gallo Resident Inspector P. 0.
Box 52 Shickshinny, Pennsylvania 18655 Susquehanna Environmental Advocates c/o Gerald Schultz, Esq.
500 South River Street Wilkes-Barre, PA 18702 John L. Anderson Oak Ridge National Laboratory Union Carbide Corporation Bldg. 3500, P. 0.
Box X
Oak Ridge, Tennessee 37830 Mr. Robert J. Shovlin Project Manager Pennsylvania Power and Light Co'.
2 North Ninth Street Al 1 entown, Pennsyl vania 18101 Matias F. Travieso-Diaz, Esq.
Shaw, Pittman, Potts Trowbridge 1800 M Street, N.
W.
Washington, D. C.
20036 Dr. Judith H. Johnsrud Co-Director Environmental Coalition on Nuclear Power 433 Orlando Avenue State College, PA 16801 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Department of Environmental Resources Commonwealth of Pennsylvania P. 0.
Box.2063
. Harrisburg, PA 17120 Ms. Colleen Marsh Box 538A, RDd4 Mountain Top, PA 18707 Mrs. Irene Lemanowicz, Chairperson The Citizens Against Nuclear Dangers P. 0.
Box 377 RDgl
- Berwick, PA 18503
ENCLOSURE 331-1 331.0 331.11 (SRP 12.3,4)
(NUREG-0578, 2..1.8.b.3 5
- 2. 1.8.c, 5 ltrs of 9/27/79 5
11/9/79 to pending OL appli-cants for criteria) 331.12 (12.2.1. 3)
RADIOLOGICAL ASSESSHEHT BRANCH You have not described an in-plant accident radiation and airborne radioactivity monitoring system as required in our standard review plan.
It is our position that the in-plant accident radiation and airborne radioactivity monitoring systems should provide personnel with the capability to assess the radiation hazard in areas which may need to be accessed during the course of an accident.
The accident monitoring systems may include the normal area radiation monitors, airborne radioactivity
- monitors, and portable radiation monitoring equipment.
The accident monitoring systems should have a usable range which includes the maximum calculated accident levels, and they should be designed to operate properly in the environment caused by the accident..
Describe your accident monitoring
- systems, and describe how your systems will meet this position.
Radiation dose rates in excess of 100 rads per hour can occur in the vicinity of spent fuel transfer tubes. 't is our position that the SFTT area should have structural barriers to prevent inadvertent access to the high radia-tion levels near the area and sufficient shielding to assure acceptable radiation levels in adjacent occupied
331-2 331.1 3 (12.1.1) areas.
Provide plan and elevation layout drawings of the SFTT areas, including these adjacent areas.
Your response should include procedures for positive access control and radiation monitoring in the areas near the
- SFTT, as well as audible and visible radiation alarm signals to be actuated if radiation fields increase above ambient levels in the area.
Describe how your spent fuel transfer tube operation meets this position.
It is our position that decommissioning will be in accordance with Regulatory Guide 8.8,
" Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations Will be ALARA". Revision 3,
- June, 1978.
Verify that decommissioning will be in accordance with Regulatory Guide 8.8 or submit equivalent alternative.
331.1 4 (HUREG-0578, 2. 1,6.b ltr of 11/9/79 for criteria) 331.15 Provide results of design review for additional shielding required to provide access to vital areas and protect safety equipment after a core degradation accident.
Provide a description of the radiation protection features (NUREG-0578, 2. 1.8.a incorporated in the system for sampling and analyzing reactor
& ltr of 11/9/79) coolant and containment atmosphere after a core degradation accident.
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