ML20116L692
| ML20116L692 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/12/1992 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 92-714, NUDOCS 9211190081 | |
| Download: ML20116L692 (2) | |
Text
-
v; r.
e VIHOINI A EI.ECTRIC AND Powr.H COMPANY HICIIMOND. VIROINIA 23201 November 12, ~992 U.S. Nuclear Regulatory Commission Serial No.92-714 Atterdion: Document Control Desk MPW/EJW Washington, D.C. 20555 Docket Nos.
50 338 50-339 Ucense Nos. NPF-4 NPF-7 l
Ge.ntlemen:
VIRGINIA ELECTrijC AND POWER COMPANY NORTil ANNA POWER STATION UNfTS 1 &_2 ElRE DETECTION INSTRUMEUATION TESTING SPEC 1hl REPORI Pursuant to Updated Final Safety Analysis Report (UFSAR) Technical Requirement 16.2.1.1.A.2.2, a Special Report is required because the Reactor Coolant Pump (RCP) non-suasNised circuits between the local panels and the Contrci Room (CR) fire panel have not been demonstrated operable every 31 days as required. The missed UFSAR Surveillance Requirement (SR) 16.2.1.1.1 fo. inside containtnent no'-
- .upervised circuits was identified during Quality Assurance Aud;t 92-15 and is a resuit of inadequi iimp!ementation of the original system testing requirements, A review c' fire protection testing proceiures indicated _that the _RCP heat detection
,j panel annunciatior, circuits were originally believed to be supervised because the
-l heat detection device initiation circuits are supervised. Supervised circuits only require a six month tem Wquency. As such me RCP heat detector panel annunciation circuits to the CR firn panel were being teted while performing enannet furetionai tests on a six month frequency tnstead of the required 31 day Wiuency ' A later changa revised the channel functional test frequency trom every a rutsnths to 00 d -
8 snutdown and did not specifically cnange the annunciation circuit testing.
Currently the re# stance temperature ddectors (PTD) for the RCP motors are being monitored as the alternative methr>d identified in the UFSAR for raonitoring RCP fire' conditions. Because of the anscciatc.d personnel safety risks involved with frequent containment entry, the RCP RTDs 4aih coctinue to be used to satisfy the UFSAR requirements until tesolution of corrective actions can be completed.
[k
- 45 170039 S/pd: pgg err /s/
/ p/
/
Sra uvoost m ua M
PDR ADOCK 05000330
. ll0
.S.
_PDR a
Evaluations are being performed to consider the following test options:
1.
Revising the UFSAR to delete or revise the frequency of testing.
2.
Modifications to change the circuit to a supervised circuit thereby changing the test frequency to 6 months and a! lowing testing from outside containment.
3.
Development of an alternative test method to verify operability.
Based upon the results of these evaluations, suitable corrective measures will be determined and implemented as appropriate.
In addition to the review of the specific concern of RCP heat detection circuit testing, UFSAR Section 16.2.1 will be revised as necessary to clarify the intent of the section Flich will preclude further misinterpretation.
This Specia: Report has been reviewed by the Station Nuclear Safety and Operating Committee and will be provided to the Management Safety Review Committee.
Should you have any quastions regarding this report, please contact us.
Very truly yours, p
b (l t,'; ; y~'
W. L. L:ewart Senior Vice President - Nuclear cc:
U.S. Nuclear Regulatory Commission Region 11 101 Marietta Strent N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Pcwer Station
__