ML18141A520
| ML18141A520 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 02/27/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM NUDOCS 8403050229 | |
| Download: ML18141A520 (6) | |
Text
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e Docket Nos. 50-280/281 and 50-338/339 Mr. W. L. Stewart FEB 2 7 1984 DISJRIBUTION:
c.]2'cket Fi 1 e L PDR Vice President - Nuclear Operations Virginia Electric and Power Company Post Office Box 26666 NRC PDR ORB#3 Rdg ORB#l Rdg DEisenhut ACRS-10 Gray Files PMKreutzer LEngle DNeighbors SVarga OELD EJordan JNGrace Richmond, Virginia 23261
Dear Mr. Stewart:
SUBJECT:
POST-ACCIDENT SAMPLING SYSTEM - NUREG-0737, ITEM II.B.3:
SURRY POWER STATION, UNITS NO. 1 AND 2 (SURRY 1&2) AND NORTH ANNA POWER STATION, UNITS NO. 1 AND NO. 2 (NA-1&2)
We have completed our review of the subject as noted above.
By our letter and safety evaluation dated December 16, 1983, we concluded that you met nine of the eleven criteria for Item II.B.3 of NUREG-0737.
By letter dated February 3, 1984, you provided additional information to address the remaining open criteria of Item II.B.3.
We now find that ten of the eleven criteria are met.
Our basis is provided in the enclosed
- safety evaluation.
The remaining criterion, which requires a procedure for estimating the extent of core damage based on radionuclide evaluation, is acceptable on an interim basis.
The final core damage procedure will be handled on a plant specific basis for Surry 1&2 and NA-1&2.
Therefore, based on the above, we consider NUREG-0737, Item II.B.3, to be complete for the subject units.
Finally, we request that plant specific procedures based on the Westinghouse Owners Group Generic Methodology be provided for our review within 60 days from the availability of the Generic Methodology.
We understand this pro-cedure should be available by August 1, 1984.
The information requested in this letter affects fewer than 10 respondents; therefore, 0MB clearance is not required under P.L.96-511.
Enclosure:
Safety Evaluation cc:
See next ORBM;~
PM~e*utzer 21.~1/84 pag!~
ORB~'ITT:
LEngle/pn 2/fl /84 Sincerely, Original signed b:y Z, G. \\Ou.I/' i fr+ 1\\'1 Sy<James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing ORBltJ~*
DNe.ii~~ors 2/;.'\\ i'84
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JRMi 11 fr 2/.l.1/84
e Virginia Electric and Power Company cc:
Richard M~ Foster, Esq.
Musick, Williamson, Schwartz, Leavenworth & Cope, P.C.
P. 0. Box 4579 Boulder, Colorado 80306 Michael W. Maupin, Esq.
Hunton, Williams, Gay and Gibson P.a. Box 1535 Richmond, Virginia.23212
.Mr. Paul W. Purdom Environmental Studies Institute Drexel University 32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 Atomic Safety and Licensing Appeal Board Panel U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Ellyn R. Weiss, Esq.
Sheldon, Hannan, Reisman and Weiss 1725 I Street, N.W. Suite 506 Washington, O. C.
20006 Mr. E.W. Harrell P.a. Box 402 Mineral, Virginia 23117 Mr. Anthony Gambardella Office of the Attorney General 11 South 12th Street~ Room 308 Richmond, Virginia 23219 Resident Inspector/North Anna
'c/ o U.S. N. R. C.
Senior*Resident Inspector
. Route 2, B_ox. 78 Mineral*, Virginia 23117 Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 Mrs. Margaret Dietrich Route 2, Box 568 Gordonsville, Virginia 22042 Mr. W. T. Lough Virginia Corporation Commis~ion
. Division of Energy Regulation P. 0. Box 1197 Richmond, Virginia 23209 Mrs. June Allen North Anna Environmental Coalition 8720 Lockmoor Circle Withita, Kansas 67207 U.S. Environmental Protection Agency Region III Office ATTN:
Regional Radiation Representative Curtis Building 6th and Wal nut Streets Philadelphia, Pennsylvania 19106 Regional Administrator Nuclear Regulatory Commission, Region II Office of Executive Director for Operations 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Old Dominion Electric Cooperative c/o Executive Vice President 5601 Cha~berlavne Road Richmond, Virg~nia 23227 r
e
- ~*-Mr:* W..-L..---Stewar.t. -
Virginia Electric and Power Company -
cc:
Mr. Michael W. Maupin Hunton and Williams Post Office Box 1535 Richmond, Virginia 23213 Mr. J. L. Wilson, Manager Post Office Box 315 Surry, Virginia 23883 Donald J. Burke, Resident Inspector Surry Power Station U.S. Nuclear Regulatory Corrmission Post Office Box 166, Route 1 Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 W. T. Lough Virginia Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia -23209 Regional Radiation Representative EPA Region II I Curtis Building - 6th Floor 6th and Wal nut Streets Philadelphia, Pennsylvania. 19106 Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 James P. O'Reilly Regional Administrator - Region II U.S. Nuclear Regulatory ColTITlission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 e
--Su.r.r...y--Eowe.r-5tatiorL Units 1 and 2
~...... **
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 _ *-
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO SURRY UNIT NOS. 1 & 2 AND NORTH ANNA UNIT NOS. 1 & 2 VIRGINIA ELELCTRIC AND POWER COMPANY DOCKET NOS. 50-280/281 AND 50-338/339 Post-Accident Sampling System (NUREG-0737), II>B.3)
.INTRODUCTION Enclosure Based on our evaluation of the Post-Accident Sampling System (PASS), we previously concluded in the SER that nine of the eleven criteria were.acceptable.
The following criteria remained unresolved:
Criterion (2) Prepare a final procedure to estimate the extent of core damage.
The procedure based on radioiodines is acceptable on an interim basis.
Criterion (10) Provide information on the frequency of calibration and testing of the PASS and of training of the operators.
By letter dated February 3, 1984, the licensee provided additional information.
Evaluation Criterion:
(2)
The licensee shall establish an onsite radiological and chemical analysis capability to provide, within three-hour time frame established above, quantification of *the following:
- _
- "P _..
a) certain radionuclides in the reactpr coolant and containment atmosphere that may be indicators of the degree of core damage (e.g., noble gases; iodines and ces1ums, and non-volatile isotopes);
b) hydrogen levels in the containment atmosphere;
e c) dissolved gases (e.g., H2), chloride (time allotted for analysis subject to discussion*below), and boron concen-tration of liquids.
d)
Alternatively,_b_1;1ve i n-1 i ne_ monitoring _capabi li.ti.es__to _
perform all or part of the above analyses.
The licensee's core damage procedure based on iodine activties is acceptable for the interim.
To fully meet Criterion (2) the licensee will provide a plant specific procedure to estimate the extent of core damage based on the generic Westinghouse owners core damage assessment methodology.
We find that the licensee partially meets Criterion (2).
Criterion:
(10)
Accuracy, range, and sensitivity shall be adequate to provide pertinent data to the operator in order to describe radiological and chemical status of the reactor coolant systems.
The ~ange, accuracy, and sensitivity, of the radiological and chemical*
analysis was given by the licensee.
Information was provided on the applicability of these procedures and instruments in the post-accident water chemistry and radiation environment.
The PASS instruments will be calibrated at least every six months.
The calibration frequency will be changed when analysis equipment demonstrate the need for an accelerated frequency.
At North Anna Units 1 & 2, the PASS, which is shared by both units, is tested every -two weeks;... **sample lines of each units are tested at least monthly_.
For Surry Units l & 2, the periodic testing program will consist of operating t~e PASS on a weekly basis, except for
- containment atmosphere, which will be bi-weekly.
At all units, periodic testing results will be compared with laboratory results to verify system operability.
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e
- In addition to the hands-on training during the periodic testing program and the Emergency Plan training cycle, the PASS technicians are retrained annually.
We determined that these provisions meet Criterion (10) of Item 11.B.3 in NUREG-0737, and are, therefore, acceptable.
Conclusion On the basis of our evaluation, we now conclude that the Post-Accident Sampling System meets ten of the eleven criteria of Item II.B.3 in NUREG-0737.
The procedure for estimation of reactor core ~amage is acceptable on ~n interim basis.
The licensee should provide a plant specific procedure to estimate the extent of core damage based on the Westinghouse Owner's Group Generic Methoaology.