ML20117P420
| ML20117P420 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/03/1985 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-TM SBN-808, NUDOCS 8506060124 | |
| Download: ML20117P420 (4) | |
Text
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L UI SEABROOK STATION Engineering Office i
Pubec Setylce of New Hampshire June 3, 1985 Now Hampshire Yankee Division SBN - 808 T.F.B7.1.2.
United States Nuclear Regulatory Cotanission Washington, D. C. 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
Reference:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444
Subject:
. Response to SER Outstanding Issue No. 8 Regarding SER Section 12.3.2
Dear Sir:
As indicated in Safety Evaluation Report Section 12.3.2, PSNH has performed a radiation and shielding design review for vital area access in-accordance with Item II.B.? of NUREG-0737. The conclusions of staff review were made subject to receipt of an FSAR amendment for this TMI Action Plan item. Accordingly, please find enclosed a copy of the revised FSAR pages which address this issue. This change will be incorporated into the FSAR in a future amendment.
If you require any additional clcrifications/information regarding the above, please do not hesitate to contact us.
Very truly yours, A/
.)
John DeVincentis, Director of Engineering and Licensing cc: Atomic Safety and Licensing Board Service List f
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P.O Box 300 Seobrook.NH03874. Tetephone(603)474 9521
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8506060124 850603 PDR ADOCK 05000443 E
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Cencral Plant Yard Areas All shielding is designed such that the dose rates in plant yard areas which are frequently occupied by plant personnel remain below 0.5 mr/hr. These areas are surrounded by a security fence, and are closed off from areas accessible to the general public for general safegt.
t.rMseliLT L2..E2.2.
12.3.3
-Ventilation The1 station ventilation system has been designed to provide a maximum of safety and convenience for' operating personnel, construction workers and site visitors working both within the station radiation control area (restricted area) and in station buildings outside the radiation control area during normal operating and anticipated operational occurrences. The potential exposure to on-site personnel and to members of the general public resulting f rom airborne radionuclides from station operation complies with 10 R Part 20 and 10 CFR Part 50, respectively_ _
n Maximum airborne radioactivity concentrations for normal operations and anticipated transients are as follows:
Within. radiation control area:
limits as specified in 10 CFR a.
Part 20, Appendix B, Table I.
~
b.
Station buildings and areas outside radiation control area:
limits as specified in 10 CFR Part 20, Appendix B, Table II.
3.
-c.
Areas'outside station restricted area: dose objectives as set forth in 10 CFR Part 50, Appendix I.
12.3.3.1 Ventilation Design Bases Descriptions of the ventilation systems for ~each building which can be expected to contain radioactive materials, including design bases, are contained in Section 9.4.
Diagrams associated with the descriptions show equipment, air-flow patterns, and expected flow rates for normal and emergency conditions.
A description ~ of the ventilation systems for the control room complex is contained in Subsection 9.4.1 and Figure 9.4-1, and shows equipment, air flow ' patterns, and expected flow rates.
Section 6.4 discusses the habitability and life support systems. of the control room complex with respect to NRC General Design Criterion 19.
In each case, air flow has been directed from areas of low potential wirborne radioactivity to areas of higher airborne radioactivity by exhausting from the areas of higher radioactivity. The ventilation rate for the areas of. higher radioactivity was determined -both from the ventilation rate required to remove. equipment heat, piping and electrical losses and w
12.3-12 L
ll.
~
, L-12.'3.2.2 Plant S'hielding to Provide Access to Vital Locations for
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Post-Accident Operations Following an accident, significant radioactivity may be released from the reactor core, presenting unusual hazards to operating
' personnel. A review was conducted to assess the-projected amount of activity released, systems involved in transport of this activity,
- effect-of the transported activity on plant dose rates and acceptability of dose rates in locations requiring access for necessary operations (vital locations).
This f assessment employed core fission product release source terms' consistent with NUREG-0737,Section II. B.2 (100% noble gas, 50% halogen,1% other fission product)., The assessment addressed both pressurized and de-pressurized accidents, and projected consequences of the release at post-accident times i'
ranging f rom 21.9l minutes to 1 year.
I The systems considered in this assessment included contain-ment spray, chemical and volume control, safety injection, residual heat removal and combustible gas control.
Using the source term and system transport information described above, _ dose rates in various plant areas were projected. These projections considered shine, scatter and radiation streaming, including effectiveness of f acility shielding.. Levels in areas which must.be accessed for operational tasks (vital-locations) were' tabulated, along with occupancy times, to verify projected exposures.are within applicable limits. - Such locations included the control room,- technical support center, post accident sample station, chemistry laboratory, switch gear. room, radwaste control
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station, radiation controlled area tunnels.and hydrogen analyzer area. Dose rates for high dose rate areas are graphically depicted
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' on area. zone maps of the plant to aid in projecting exposures for potential post-accident. operations not explicitly identified in the.
vital location table. Results of these projections demonstrate pro-jected exposures in vital locations are within the GDC-19 and' d
NUREG-0737 (Item II. B.2) criteria.
The assessments described above were incorporated into the Post-Accident Dose Engineering Manual, which is used in planning for post-accident operations. Rational for not. including several.
areas noted in NUREG-0737 (Item II-B.2) are delineated in this manual. EA copy of the manual was provided to the NRC. The information in this document will be f actored into the overall post-accident response actions.
L
.J William S.' Jordan, III Donald E. Chick Diane - Curran -
Town Manager
-Harmon, Weiss & Jordan Town of Exeter
.20001 S. Street, N.W.
10 Front Street Suite 430 Exeter, NH 03833
' Washington,~ D.C.
20009 Brentwood Board of Selectmen Robert G..Perlis RED Dalton Road Office -of the Executive Legal Director Brentwood, NH 03833 U.S. Nuclear Regulatory Commission Washington,~ DC 20555 Richard-E. Sullivan, Mayor City Hall Robert A. Backus, Esquire Newburyport, MA 01950 i
' 116 Lowell. Street P.O.' Box 516 Calvin A. Canney Manchester,'NH 03105 City Manager City Hall Philip Ahrensc Esquire 126 Daniel Street Assistant Attorney General Portsmouth, NH 03801
- Augusta,~ ME 04333 Dana Bisbee, Esquire Mr. John B. Tanzer Assistant Attorney General
' Designated Representative of Office of the Attorney General g.
the Town of Hampton 208 State House Annex 5 Morningside Drive Concord, NH 03301 iHampton, NH 03842 Anne Verge, Chairperson JRoberta C. Pevear Board of Selectmen Designated Representative of Town Hall i.
.the Town _of Hampton Falls South Hampton, NH 03827 L
' Drinkwater Road.
Hampton Falls, NH.03844 Patrick J. McKeon Selectmen's Office L
Mrs. Sandra Gavutis 10 Central Road Designated Representative of Rye, NH 03870 theLTown of Kensington l
RFD 1:
Carole F. Kagan, Esquire L
East Kingston, NH '03827 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Jo. Ann Shotwell, Esquire Washington, DC 20555 Assistant Attorney General Environmental Protection Bureau Mr. Angi Machiros L
Department of the Attorney General Chairman of the Board of Selectmen l
One Ashburton Place, 19th Floor Town of Newbury Boston, MA 02108 Newbury, MA 01950 s-l L
Senator Gordon J. Humphrey Town Manager's Office-l U.S. Senate Town Hall - Friend Street l _
Washington, DC 20510 Amesbury, MA 01913 L
.(ATTN: Tom Burack)
Senator Gordon J. Humphrey
. Diana P. Randall 1 Pillsbury Street 70 Collins Street Concord, NH 03301
.Seabrook, NH 03874 (ATIN: Herb Boynton) s