ML18141A269
| ML18141A269 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/05/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8312150193 | |
| Download: ML18141A269 (3) | |
Text
_...
Docket Nos. 50-280 and 50-281 Mr. W. L. Stewart Vice President-Nuclear Operations Virginia Electric Power Company Post Office Box 26666 Richmond, Virginia 23261
Dear Mr. Stewart:
DISTR.TION:
Docket File NRC PDR L PDR D Eisenhut OELD NSIC E Jordan J Taylor ACRS-10 J Neighbors S Varga C Parrish Gray File ORB #1 Rdg.
We are reviewing your submittal dated September 13, 1983, related to boron concentration reduction in the boron injection bank for Surry Power Station, Unit Nos. 1 and 2.
We find that we need additional information as specified in the enclosure.
This request was relayed to your staff informally on November 14, 1983.
Please note that additional requests may be made as our review continues.
It is requested that you respond within 14 days of receipt of this letter or provide us with your schedule for responding.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents, therefore, 0MB clearance is not required under P.L.96-511.
8312150193 831205 PDR ADOCK 05000280 P
Enclosure:
As stated cc w/enclosure See next page ORB#,'
J Neig ors 12/'.)_
3 Sincerely, OriSiool signed bit
.Sc A.0 Varga Steven A. Varga, Chief Operating Reactors Branch No. 1
e
~r. w:L. Stewart 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 P. O. Box 315 Surry, Virginia 23883 Donald J. Burke, Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission Post Office Box 166 Route 1 Surry, Virginia 23883 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 Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
jjjl I
.J,'dll, Request for Additional Information Surry Power Station Units 1 & 2
- 1.
Provide the details and justification of the reactivity feedback model and the mixing coefficients utilized in the main steam line break analysis contained in your submittal of September 13, 1983;
" 2~*,*.
Clarify your proposed heat tracing requirements for the safety
-injec-tfon (SI) lines assuming implementation of your recommendation to reduce the boric acid concentration.
On page 9 of your submittal you state that lowering the boric acid concentration in the BIT to O PPM eliminates the need to maintain heat tracing on the associated SI piping.
Discuss whether the normally stagnant sections of the SI piping between the normal charging pump discharge and the closed isolation valves upstream of the BIT can contain concentrated boric acid due to operator error or equipment failure (e.g., valve leakage).
If this can occur explain how precipitation of the boric acid and consequent pipe blockage is avoided.
Include the type and frequency of checks performed.
- 3.
Provide the results of the offsite dose calculations as a consequence of your revised main steam line break analysis for both the case of a preaccident iodine spike and concurrent iodine spike.
Provide pertinent_
assumptions utilized in your calculations, including primary to secondary leakage.