ML19345F301
| ML19345F301 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/23/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Groce R Maine Yankee |
| References | |
| NUDOCS 8102170145 | |
| Download: ML19345F301 (4) | |
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UNITED STATES
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,,i W ASHINGTON, D. C. 20555 g.k'W'[/. !
January 23, 1981 Docket No. 50-309 to i rs
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Mr. Robert H. Groce
$( da Senior Engineer - Licensing g IU '3 o $31 *' 9 Maine Yankee Atomic Power Company a
H 1671 Worcester Road p%[.se p o
Framingham, Massachusetts 01701 gc
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Dear Mr. Groce:
By letter dated February 5,1979 you responded to the NR hest ~iff'd 30, 1978 regarding the potential consequences of a esttrIiIrfe November The staff has reviewed Fuel Handling Accident Inside Containment (FHAIC).
this submittal and your March 18, 1977 response to our January 17, 1977 request for information on the same subject. As a result of our review, we have determined that additional infonnation and restrictions are necessary for us to conclude that the potential consequences of a FHAIC are appropriately within the guideline of 10 CFR Part 100.
-4 3
sec/m,
The staff was unable to verify that the X/Q value of 5.36 X 10 which you used in your cal ulations, is appropriate and, therefore, we assumed a X/Q of 7.7 X 10 4 sec/m3 in our independent calculations. Using the staff's assumed X/Q value, we calculate a thyroid dose of 163 Rem at As stated in our November 30, 1978 letter, the the Exclusion Area Boundary.
staff has defined the statement " appropriately within the guidelines of 10 CFR Part 100 to be 100 Rem thyroid."' This is based on the probability of FHAIC relative to other events which are. evaluated against 10 CFR Part 100 The staff's review also disclosed that appropriate restrictions guidelines.
are not required for containment integrity during the handling of irradiated fuel within the containment.
Therefore, we request that you provide us, within 30 days of your receipt of this letter, the following:
Verification that the X/Q value which you used in your calculations 1.
is the appropriate value, and I
Proposed technical specifications to ensure adequate containment 2.
integrity during movement of irradiated fuel within the containment.
We have enclosed a copy of the CE-STS concerning Containment Building Penetrations during fuel handling operations within the contairment for your guidance in preparing the requested techniccl speci?! cation.
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l 2-Mr. Robert H. Groce If you have any questions on this subject, please contact Mr. P. Wagner at 301-492-7072.
Sincerely, L
co m Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
As stated cc: See next page i
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N Maine Yankee Atomic Power Company Mrs. L. Patricia Doyle, President cc:
E. W. Thurlow, President SAFE POWER FOR MAINE Maine Yankee Atomic Power Company Post Office Box 774 Camden, Maine 04843 Edison Drive Augusta, Maine 04336 First Selectman of Wiscasset Mr. Donald E. Vandenburgh M'unicipal Building Vice President - Engineering U. S. Route 1 Yankee Atomic Electric Company Wiscasset, Maine 04578 20 Turnpike Road Di. rector, Criteria and Standards Iivision Westboro, Massachusetts 01581 Office of Radiation Programs (ANR-460)
John A. Ritsher, Esquire U.S. Envircrhental Protection Agency Washington, D.C.
20460 Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 U. S. Enviromental Protection Agency Region 1 Of fice Mr. John it. R. Paterson ATIN:
EIS COORDINATOR Assistant Attorney General JFK Federal Building State of Maine Boston, Massachuset'ts 02203 Augusta, Maine 04330 Stanley R. Tupper, Esq.
Mr. Nicholas Barth Tupper and Bradley 102 Townsend Avenue Executive Director Sheepscot Valley Conservation Boothbay Harbor, Maine 04538 Association, Inc.
P. O. Box 125 David Santee Miller, Esq.
Al an, Maine 04535 213 Morgan Street, N. W.
Wistassett Public Library Association Mr. Paul Swetland High Street 04578 Resident Inspector / Maine Yankee Wiscasset. Maine c/o U.S. NRC Mr. Torbert H. Macdonald, Jr.
P. O. Box L Office of Energy Resources Wiscasset, Maine 04578 State House Station #53 Augusta, Maine 04333 Mr. Charles B. Brinkman Manager - Wa:hington Nuclear Robert M. Lazo, Esq., Chairman Operations Atomic Safety and Licensing Board C-E Power Systems U. S. Nuclear Regulatory Comission Combustion Engineering, Inc.
Washington, D. C.
20555 4853 Cordell Ave., Suite A-1 Bethesda, Maryland 20014 Dr. Cadet H. Hand, Jr., Director Bodega Parine Laboratory University of California Bodega Bay, California 94923 State Planning Officer Mr. Gustave A. Linenberger Executive Department Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission f8 t te et Washington, D. C.
20555 Augusta, Maine 04330
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REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
The equipment door closed and held in place by a minimum of four a.
- bolts, b.
A minimum of one door in each airlock is closed, and Each penetration providing direct access from the containment atmosphere c.
to the outside atmosphere -shall be either:
1.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Be capable of being closed by an OPERABLE automatic containment purge valve.
APPLICABILITY:
During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:
Verifying the penetrations are in their closed / isolated condition, a.
or b.
Testing the containment purge valves per the applicable portions of Specification 4.6.4.2.
CE-STS 3/4 9-4 0CT 17 580
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