ML19274D475
| ML19274D475 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 01/16/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| TASK-02-02.C, TASK-08-03.B, TASK-2-2.C, TASK-8-3.B, TASK-RR NUDOCS 7902010220 | |
| Download: ML19274D475 (8) | |
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UNITED STATES y"
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20565 e
January 16, 1979 Docket No. 50-213 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
Enclosed are copies of our draft evaluation of two Systematic Evaluation Program Topics. You are requested to examine the facts upon which the staff has based its evaluation and respond either by confirming that the facts are correct, or by identifying any errors.
If in error, please supply corrected information for the docket. We encourage you to supply for the docket any other material related to these topics that might affect the staff's evaluation.
It would be helpful if your comments were received within 30 days of the date you receive this letter.
Sincerely,
~
9/w%5v Dennis L. Zieman hief Operating Reactors Branch #2 Division of Operating Reactors
Enclosures:
Topics II-2.C VIII-3.A cc w/ enclosures:
See next page 79020102do O
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Mr. W. G. Counsil January 16, 1979 cc w/ enclosures:
Day, Berry & Howard Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 Superintendent Haddam Neck Plant RFD #1 Post Office Box 127E East Hampton, Connecticut 06424 Mr. James R. Himme1 wright Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 K M C, Inc.
ATTN: Jack McEwen 1747 Pennsylvania Avenue, N. W.
Suite 1050 Washington, D. C.
20006
Haddam Neck Plant Topic II-2.C Atmospheric Transport and Diffusion Characteristics The objective of this review is to determine the appropriate on-site and near-site atmospheric transport and diffusion characteristics necessary to establish conformance with the 10 CFR Part 100 guide-lines.
In particular, the short-term relative ground-level air concentrations (X/Q) are used to estimate offsite exposures resulting from postulated accidents.
The most recent staff evaluation of short-term X/Q values at the Connecticut Yankee site was performed in November 1977. At that time, two years (January 1975 - December 1976) of onsite meteorological data were used in the calculations of short-term X/Q values. Wini speed and direction were measured at the 10m level, and atmospheric stability was defined by the measurement of vertical temperature gradient between the 10m and 60m levels.
The atmospheric dispersion model used for the November 1977 evaluation is a modification of the model described in Regulatory Guide 1.4 which incorporates the results of recent atmospheric tracer tests and which considers atmospheric dispersion conditions as a function of direction. Specifically, this direction-dependent model considers the following effects:
. (1) Lateral plume meander, as a function of atmospheric stability, winc speed, and distance from the source, during periods of low wind speed, and neutral and stable atmospheric conditions.
(2) Exclusion area boundary distance as a function of direction from the plant (3) Atmospheric dispersion conditions when the wind is blowing is a specific direction (4) The fraction of time that the wind can be expected to blow into each of the 16 compass directions The direction-dependent model used for the November 1977 evaluation is described in detail in DRAFT Regulatory Guide 1,XXX, " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants" (September 1977), The following X/Q values were determined using this model for an assumed ground level release for various time periods at the exclusion area boundary and the outer boundary of the low population zone:
3 Tirne Period Distance & Direction X/Q sec/m 0-2 hours West 0 550m, and 1.0 x 10 3 west-northwest 0 530m
-5 0-8 hours LPZ (11e65M) 1.5 x 10
. 3 Time Period Distance & Direction X/Q sec/m 8-24 hours LPZ (11265m) 1.0 x 10-5 1-4 days LPZ (11265m) 4.4 x 10-6 4-30 days LPZ (11265m) 1.3 x 10-6 Subsequent to the November 1977 evaluation, the Hydrology-Meteorology Branch Position HMB-BTP-2, Revision 1 (August 2,1978), was approved for licensing evaluations. This branch position modifies the pro-bability level to be considered in the direction-dependent model for each sector (from 0.3% to 0.5%) and also requires the calculation of a X/Q value averaged over the site at a 5% probability level; this value is to be used if it exceeds the li.miting sector X/Q yalue.
Using the modified direction-dependent model for an assumed ground-level release we calculate the highest X/Q value for the 0-2 hour time period to be 8.4 x 10-4 sec/m at 530m west-north-west of the plant.
3 X/Q values for various time periods at the outer boundary of tiie low population zone have not been recalculated at this time because the difference from the November 1977 evaluation is expected to be relatively small (about 10%).
We conclude that the relative concentration value of 8,4 x 10-4 sec/m for the exclusion area boundary and thoselisted in the table above for a
, the LPZ are appropriate for estimating offsite exposures resulting from postulated accidents.
This completes the evaluation of this SEP topic. Since this eval-uation conforms to current licensing practice, no additional SEP review is required.
SYSTEMATIC EVALUATION PROGRAM BATTERY CAPACITY TESTS HADDAM NECX DOCKET NO: 50-213 Topic VIII-3.A Station Battery Test Requirements The objective of this review is to assure that the onsite Class IE battery capacity to supply all safety related D-C loads is verified by periodic testing.
The testing should be in accordance with IEEE Standard 450-1975, IEEE Standard 308-1974, BTP EICSB 6 and the " Standard Technical Specifications for Westinghouse Pressurized Water R: actors" (NUREG-0452). The required tests are as follows:
1.
At least once per 18 months, during shutdown, a _ battery service test should be performed to verify tilat the battery capacity is adequate to supply and maintain in operable status all of the actual energency loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2.
At least once per 60 months, during shutdown, a battery discharge test should be performed to verify that the battery capacity is at least 80%
of the manufacturer's rating.
The technical specifications for the Haddam Neck Nuclear Station do not include any requirements for station battery tests. Therefore, the Haddam Neck Nuclear Station does not comply with current licensing require-ments for station battery tests.
This deviation will be evaluated in the context of the Design Basis Events (DBE) that rely upon these components for mitigating the consequences of the DBE.
If this deviation is determined to be unacceptable, the Technical Specifications will be appropriately revised.
References 1.
"Haddam Neck Technical Specifications", Connecticut Yankee Atomic Power Company.
2.
Standard Review Plan, Appendix 7-A, BTP EICSB 6, " Capacity Test Requirements of Station Batteries - Technical Specifications", U. S.
Nuclear Regulatory Commission.
3.
"IEEE Standard Criteria for Class IE Power Systems for Nuclear Power Generating Stations", Std. No. 308-1974, The Institute of Electrical and Electronics Engineers, Inc.
4.
"IEEE Recanmended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Std. No. 450-1975, The Institute of Electrical and Electronics Engineers, Inc.
5.
" Standard Technical Specifications for Westinghouse Pressurized Water Reactors", NUREG-0452, U. S. Nuclear Regulatory Commission.
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