ML20098E209
| ML20098E209 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/18/1992 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| CL-624, NUDOCS 9206020027 | |
| Download: ML20098E209 (3) | |
Text
.
. Georgia Ibwet Company Y'
333 Piedmont Avenue-Atlanta, Geotgia 30308 Telephone 404 526-6526 Ma!!ing Address:-
Fbst Off:ce Dox.154$
Atlanta. Georgia 30302 h
3 - P 3 L,H Georgialbwer L. T. Gucwa t*e seut'em sectric system Manager Nuclear Sately
_and Licensing I
SL-624-0494C April 18,1986 U. S. Nuclear. Regulatory Commission
REFERENCE:
Office of Inspection and Enforcement 50-366 Region II - Suite'2900 RII: YLB Marietta Street, NW Atlanta,-Georgia 30323 ATTENTION: Dr. J. Nelson Grace g.3g g, Sentlemen:
Several telephone conversations were held with _ members of' your; staff and NRR on Aprill5_and,Aptil;16,1986, regarding the operability of the
'Re&ct6r!CcrmIsolation4 Cooling (RCIC) *SystemY #steamisupplyvisolation.
valve 2E51-F008; presently + installed 4 ontHatchtunitL2.
Thel purpose of this letter is to document these conversations by:
q 1.
Describog the problem.
4 2
Describing the testing that will be. performed to assure' i
that the valve is operable.
3 Discussing the _ additional surveillance which will! be:
performed to show that the valve. remains operable.
i 4
Addressing NRC staff statements iregarding assurance that-l plant LCOs on. other systems or degraded plant conditions:
1-will not adversely affecte the operability 1of the RCIC.
system.
4 Problem Description On March 29, 1986, control room operators. noted ~ that _ the position:
indicators for valve E51-F008 were both illuminated-and,- hence. the valve position (open or closed) could not be-: verified. _ Upon testing the valve.-
L"
- to assure operability, it was discovered that the valve:11mit' switches-and torque switches did nottprevent.the motor._: from driving the' valve = to the locked rotor-positica.
However, testing of. the valve -assured that the valve would perform (close) within. the-Technical, Specifications limits.
9206020027 920418 DR-ADOCK 0500 6
3 p-p-
103-
r Georgia Power b U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement ATTENTION: Dr. J. Nelson Grace April 18, 1986 Page Two Testing Requirements In our discussions with the NRC, we described special testing that could be perfonned to assure that the valve would perform its safety function (close when required) and maintain a leaktight barrier.
The testing would consist of the following elements:
1.
Inboard isolation valve 2E51-FOC7 would be verified closed.
2.
Valve 2E51-F008 would be stroked to the open position and the valve opening time recorded.
'!al ve open would be determined by monitoring-the valve motor amperage.
Cautions would be issued requiring that the amperage not be allowed to reach " locked rotor" amps.
3 Valve 2E51-F007 would be opened, which would pressurize the RCIC steam supply line to the admission valve (2E51-F119).
4 Yalve 2E51-F008 would then be closeu and the stroke time measured by the same methods described in 2.) above.
5 Leaktightness of val ve 2E51 -F008 would be assured by confirming that the steam line drain pot high-level annunciator is off; by opening valve 2E51-F119; and by confirming that the RCIC system pressure decreases, that the RCIC turbine does not spin (excluding slight windmilling), and that no steam pressure exists in the steam pot level switch line.
6 The admission valve would then be closed, and leaktightness of valve 2E51-F008 would be assured by monitoring the steam pressure in the steam line and verifying that pressure does not increase beyond allowable values.
Assurance that the RCIC system will perform its function of injecting water into the vessel would be provided by opening valves 2E51-F007 and F008, and by running the RCIC operability test per plant procedures.
Additional Surveillances_
To assure that valve 2E51-F008 remains in its proper position, current to the valve motor wou1( be recorded, and the recorder would be monitored on each shift.
Standing orders would be issued to assure that this monitoring is accomplished.
In addition to monitoring the valve 0494C
O' a
k Georgia Power z U. S. Nuclear Regulatory Comission Of fice of Inspection and Enforcement ATTENTION: Dr. J. Nelson Grace April 18, 1986 Page Three position, a heightened awareness of the operability of the RCIC system, its supporting systems, and the RCIC equipment area coolers and their supporting systems would be maintained until valve 2E51-F008 is returned to its original condition.
Standing orders would he issued to _ this effect.
LCOs and Other Plant Degraded Conditions Standing orders would be issued requiring that the impact of plant LCOs, or other degraded conditions, be evaluated to determine the impact, if any, upon the safety of the plant, taking into consideration the status of valve 2E51-F008.
Based upon the successful performance of the testing (successfully completed on April 17, 1986) and the implementation of the surveillance program described above, Georgia Power Company concluded, and the NRC agreed, that valve 2E51-F008 would be deemed operable.
We expect to operate the unit in this configuration until the next scheduled shutdown, which should occur at the end of May 1986 Should j
this status change, Georgia Power Company will promptly notify the NRC.
If you should have any questions in this regard, please contact this office at any time.
Very truly yours, us-/L L. T. Gucwa JDH/lc c: Georgia Power Company Mr. J. P. O'Reilly Mr. J. T. Beckham, Jr.
Mr. H. C. Nix, Jr.
NRC Region II Mr. P. Holmes-Ray NRC - NRR Iir. H. R. Denton Mr. R. M. Bernero Mr. D. R. Muller 0494C um
-.