ML19308A445
| ML19308A445 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/28/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML19308A443 | List: |
| References | |
| NUDOCS 7910180056 | |
| Download: ML19308A445 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION f %.. [/, I wAsm ucTon. o. c. 20sss
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September 28, 1979 Occket l'es. 50-338 50-339 97' D
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!'r. W. L. Proffitt IEql 7
0 Senior Vice President - Power Virginia Electric and Power Company 1"L l
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Post Office Box 26666 Richmond, Virginia 23261
Dear Mr. Proffitt:
During a meeting with you the morning of September 26, 1979, we reviewed with you a number of areas where we expected to recuire additional infor-mation from you concerning the safety injection event at tiorth Anna Unit 1 on September 25, 1979.
Please provide written responses to the enclosed information requests. This infomation should be provided as soon as the'necessary work can be done by your staff but no later than 30 days prior to your planned return to power from the current plant outage, which we understand -you are scheduling.for about 12 weeks from now.
It is expected that any actions you take will be fully reflected in the design and procedures to be implemented on fiorth Anna Unit 2.
Si ncerely,
/
NY
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A. Schwencer, Chief Operating Reactors Branch #1 i
Division o.f Operating Reactors 4
Enclosure:
Request for Information-cc:
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NORTH ANNA UNIT NO. 1 DOCKET NO. 50-338 REQUEST FOR ADDITICNAL INFCRMATION RELATED TO THE SEPTEMEER 25, 1979 EVENT 1.
Perfora an engineering analysis of the Septenber 25,1979 event, identifying all of the significant initial conditions, and provide a comparison with events analyzed in Chapter 15 of the North Anna FSAR especially with regard to assumed initial conditions, boundary conditions and system failures.
2.
' Identify all plant procedures (number, title, date) used at various phases of the event.
Provide a summary describ 'ng the extent to which these procedures were used and why this use wa: considered appro-priate.
3.
Describe, specifically, the criteria that you used to detemine that natural circulation was achieved following reactor coolant pump Identify the instruments relied upon and their readings.
trip.
Provide the schedule by which formal written natural circulation cool-dcwn procedures will be available to plant operators.
Provide a description of the reactor coolant punp seal perfomance during the event.
5.
Provide an analysis of the actual pressurizer level, including the minimum level reached.
6.
Indicate how many times the power operated relief valve on the pressurizer cycled and what indications were available to the operator (e.g., quench tank level, tail pipe temperature, valve position indication,etc.).
Explain the apparent second cycling of the PORV approximately 25 minutes after the first interval (see pressurizer pressure strip chart record).
7.
Quantify the mass loss through the PORV and explain how this was d eterm.ined.
8.
Considering the nature of how plant parameters (e;g., pressure temperature, pressurizer level, etc.) varied and'were displayed to the operator during the event, indicate how and when you would have decided to terminate the high pressure injection based on the H?I termination criteria recommended by k'estinghouse.
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. Ir.dicate incore temperature readines takereduring :he avent.
9.
Provide details as to magnitude, time, anelociticn.
Describe the extent to which you consulted with Westir; house during 10.
and inmediately following this event.
Provide a detailed chronology of significant events during the period 11.
from the initiating event at approximately 05'4 hcurs :hrc gh return of activity in the auxiliary building to below MPC limits.
Ycur alarm typewriter printout indicates that for at least one hour
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prior to the turbine trip, the containment su p level continually 12.
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cycled to the alarm setpoint.
Why?
Identify the number of VEPC0 personnel working in the control room during 13.
the first 30 minutes of the event.
State whether the site emergency plan was activated in any form.
14.
Describe the extent to which the events which occurred at North Ann 16.
had teen sinulated at the Surry Sinulator and dem:nstrated to North 25, 1979.
Dis:uss the training Anna operators, prior to September which North Anna operators have received at the Surry Simulator en tripping RCPs, natural circulation anc Bulletin 79-063 lipI requirements.
Explain in detail the uncontrolled reactor ccolant activity release 16.
directl,y to the auxiliary building.
Include why it happened, how it was detected, its release path (s),
how long it continued, the amount, ty;e and form (licuid, a.
gaseous, particulate) of activity released, persennel exposures at the site and potential dose rate at the site boundary and beyond.
- b. ! Given the inadvertent operator error, equipment failure, or combination thereof, in.volved on Septemb'er 25, 1979, state whether an uncontrolled release would have been pr,evented had the piping to the process vent from the high level waste drain tanks been installed as called for in the plant desien rather than in the as-found conditions.
If the answer to b abcVe is in the negative, ;rc;cse a design modification that will prevent a future uncentrclied release c.
of activity outside containment.
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3 17.
The FSAR indicates that a high level in the '/CT will alarm in the control room and divert the letdcwn stream to -he beren recovery Did any part of this alarm and diversior, system activate system.
price to or during the time that the VCT relief valve was open (assuitad to be approximately 10 minutes)? tlcul d such activity affect the release in 16' ebove?
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