ML20236X335
| ML20236X335 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/04/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-472C, NUDOCS 8712090126 | |
| Download: ML20236X335 (4) | |
Text
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i VIRGINIA.ELucTurc Ann POwnn COMPANY RICHMONI),VIHOINIA 2 3 2 0s1 i
W. L. STvswar vic= P===== n December 4, 1987 Nors.=Au orsmATMNN United States Nuclear P.egulatory Commission Serial No.
87-472C Attention: Document Control Desk NA/SAH/bgp 2
Washington, D.C.
20$55 Docket Nos.
50-338 50-339 License Nos.
NPF-4 NPF-7 Gentlemen.
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 i
SUPPLEMENTAL INFORMATION REGARDING
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'SGTR EVENT AND ANNUAL DRILL CRITIQUES I
1 By letter dated October 9, 1987, Virginia Electric and Power Company formally i
requested an exemption from the requirements of 10CFR50.47 and 10CFR50, Appendix E to perform an exercise of the Station Emergency Plan in 1987. The basis for this request was provided in our letters of August 3,
1987 and September 11, 1987,-which discussed the successful emergency response actions I
taken by the Company in response to the July 15, 1987 Steam Generator. Tube Rupture event at North Anna.
Following receipt of our October 9, 1987
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exemption request, members of your staff contacted the Company in order to 1
obtain supplemental information.
Specifically, we were requested to provide s l
definitive commitment for the resolution of problems identified as a result of j
interviewing personnel who were involved in our response to the SGTR event.
In addition, we were requested to delineate those improvement items identified
.l during the critiques of the Fire, Medical, and Post Accident Sampling System 1
Drills which were conducted some time after the SGTR event.
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The specific improvement items resulting from the SGTR event were previously submitted to the NRC in Section 13 of our letter dated September 11, 1987.
The corrective actions to resolve these items will be completed no later than prior to the next annual Emergency Plan exercise, and in fact are currently scheduled to be completed by January 31, 1988.
The specific improvement items resulting from the critiques of the supplemental drills conducted subsequent to the SGTR event are given in l
Attachments 1 and 2.
Overall, the corrective actions that will be taken to address these items will be completed prior to the next annual Emergency Plan exercise, and more specific completion datas are given in the Attachments.
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Should you require any additional information, please contact us.
Very truly yours, d
W. L.
art ec:
.U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station l
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7 ATTACHMENT;1
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^ FIRE / MEDICAL DRILL-.
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f,L CRITIQUE IMPROVEMENT ITEMS:
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I.
NARRATIVE-A c'ritique < involving controllers,' observers, and key partic'ipants; was; conducted-immediately.following the. conclusion of, the L Fire / Medical:
Drill:enLAugust. 13, 1987. The. purpose of: the critique was... to. discuss :
effectiveness of the response to.lthe drill; r and-to identify,and.
c L elaborat'e on. weaknesses. that were observed. - It was determined that the~
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- objectives of the drill were satisfactorily achieved,L and that a numberE of positive actions, identified below,' wereLobserved:
la HP response'to both:the fire :and' medical event 'was ' excel' lent.
Contamination control.was.very satisf actory,.and. handling of. they first aid, patient was professional.
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2.
Response by the Control Room staff.was' effective in termslof event command:'and-control.-
Response.was. timely,'and procedures were' initiated as appropriate.
- 3.. The usef of: visual aids -(mulage ; kit) was. excellent a as :- f ar; as.
- injecting realism :intoa the medical event.- Individuals initially-responding.to'theLemergency thought'that the injuries were: real.
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not simulated. This was a tremendous. benefit to the First Aid Team-1 s
N and, contributed:to'the Team's successful-response.,
- 4. 1 Response by the, Mineral Fire Department.and'LRescue Squad' was-
. timely, and was effec'tively coordinated with'the station's response.
' teams. These response groups l fully. demonstrated.. their capability to supportLNorth. Anna'in theLevent of an actual emergency..
I' V II.
IMPROVF'ZNT-ITEMS AND CORRECTIVE ACTION SCHEDULE-Sigt.icant items ' identified as requiring corrective action have been
, pie.ed on~the Commitment Tracking System for resolution.
Corrective e cions, for the critique items listed _below, will be addressed during-ne regular quarterly and annual retraining sessions.
1.
.The Fire Brigade, First Aid Team, HP, and the Search Team were all using the same (only) radio frequency. Due to the high traffic and congestion, it was difficult' to hear messages. Too much time' was i
expended while awaiting turns'to talk.
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a-ATTACHMENT 2;
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w POST--ACCIDENT SAMPLINC' SYSTEM DRILL s
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CRITIQUE IMPROVEMENT ITEMS U.
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NARRATIVE
, 30
.As critique was conducted immediately' following ' the - termination' of the l Post-Accident Sampling System ; Drill c'onducted on. August :14,.1987..
-Controllers.. observers. and. key participants' assembled:to discuss the overalliresponse> activities.-~and to identify l weaknesses' which were oboerved.
Furthermore ;theselindividuals were encouragedito' recommend-
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enhancements which would-ultimately-atrengthen Ethe. response effort.
-Through-the: ' critique ; process,_ it Lwas. determined..that the. drill objectives.were satisfactorily achieved.
Specifically. a111guid _ sample wasL:obtained and; analyzed as required,- procedures 'were ~ appropriately.
implemented, and communications between.Lemergency responsefpersonnel!
were effective..
II.
IMPROVEMENT ITEMS AND CORRECTIVE' ACTION SCHEDULE (Items requiring 1 corrective;. action were! placed -in the Commitment Tracking Sys tem ; for. resolution. Corrective actions'for items listed in-Esection "A" ;below have been completed. :Those items '11sted in section "B" are; scheduled to:be resolved by December 31, 1987.-
A.-
- 1.. Air ; bottle regulator was past its calibration Ldue.
date (5/18/85).
2.
The-1 panel high pressure ' alarms were not tested since ' they were-not in service.
3' Valve 1-PG-153 has two different mark number tags.
. 4 ~. The cask does not have an eye bolt. connection for a safety rope.
ii 5.
Technicians did not initial ~ steps af ter opening / closing valves
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as provided for in OP-12.3.
B.- 15 Air and-nitrogen bottle pressure
'(initial condition) 1r '
verification cannot be performed without manipulating valves (1-0P-12.3, Step 4.1.4).
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Performing: simultaneous = lineups of the. local and remote panels i
(allowed under' 1-0P-12.3) 'would. speed up the time to take a sample.
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' 3.. In OP-12.3, there should be: n more distinct delineation between l
Unit l' and Unit' 2 valves.
The ' existing' method of using l
_ parentheses-is confusing.
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