ML16340B931
| ML16340B931 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/21/1981 |
| From: | Manning W NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| References | |
| NUDOCS 8107240080 | |
| Download: ML16340B931 (6) | |
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OFFICE OF THE COMMISSIONER ib, MEMORANDUM TO TH Z~S I
(P UNITEDSTATES NUCLEAR REGULATORY COMMIS iON INGTON, D.C. 20555 cg'l3 w
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3 ly 21, 1981 Op~
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%r FROM:
William J. Manning, Legal Assistant t Commissioner Gilinsky SERVEC JUL 28 tgef'UBJECT:
TOUR OF DXABLO CANYON FACTLETY This memorandum is a summary of Commissioner Gilinsky's tour of Diablo Canyon Units 1 and 2 on July 10, 1981.
Since this is a contested
- case, a copy of this memorandum will be sent to the parties and the Licensing Board.
Commissioner Gilinsky was accompanied by Marvin M. Mendonca, NRC's Resident inspector, Talbert Young from NRC's Region V office, Edward C. Abbott, an ACRS Fellow, Glenn Kelly from-NRC's Office of Policy Evaluation, and William J.-Manning, Commissioner Gilinsky's legal assistant.
PG&E was represented by R.
C.
Thornberry, Jim -Schuyler, Malcom Furbush, John
- Hoch, and James-Schiffer.
Tn addition, various members of the Diablo Canyon staff joined portions of the tour.
The Joint Zntervenors were represented by Joel Reynolds and Sandra Silver.
Governor Brown was represented by Phillip Greenberg and Dick Hubbard.
The parties'epresentatives accompanied the tour, except for the visit of the fuel building which was limited to Commissioner Gilinsky, Marvin Mendonca, Edward Abbott, Glenn Kelly, and John Hoch.
The tour began at about 8:15 a.m.
After completing the security formalities, the group saw the Unit 1 diesel generators.
The air starting solenoids were point.ed out and the starting sequence explained.
The group then toured the Technical Support Center located in the turbine building seismic
- buttress, seeing the laboratory, ventilation equipment
- room, and offices.
PG&E's representatives pointed out the telephones for communicating with the Region and Bethesda and explained the roles of the Technical Support Center and the Off-Site Center.
A person from PGGE's records department gave an explanation of the operation of the film and microfiche document retrieval system and of its computerized index.
R.
C. Thornberry demonstrated the control-room video camera
- system, whose monitors a'e located in the Technical Support Center.
Two PG&E computer operators gave an explanation of g0 the Technical Support: Center computer system.
8107240080 8i0721 PDR ADQCK 05000275 G
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The group then went through the turbine building to the Unit
- 2. Reactor building.
Some members of the group climbed to the top of the pressurizer to see the Unit 2 PORV.
The group climbed down into the Unit 2 reactor vessel.
Some members crawled through the hot and cold leg pipes.
John Hoch pointed out that the technical specifications allowed the containment purge valves to be open for 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> per year.
After leaving the Unit 2 containment, the group returned to, the Unit 1 Diesel Generators.
The Unit 1 number 2 diesel generator was started up in accordance with a routine surveillance test.
The PGGE representatives stated that the diesels had been seismically qualified.
The, diesel generator missile barriers were pointed out.
The group then went into the turbine building to look at the steam dump (bypass)
- valves, the sea water side of the main condenser, and the main feedwater pumps.
The group next went to the Unit 1 and 2 control room.
PGGE provided a demonstration of the Emergency Assessment
Response
- System, a computer system intended to be used in predicting off-site exposures during an accident.
Zn response to a question by'ommissioner Gilinsky, PG&E explained that. the operators were trained to run this system.
Bob Patterson, the plant superintendent, explained that if the automatic data entry system broke down, an auxiliary operator would be sent to the back panel to record the radiation monitor readings.
Patterson also explained that although the monitors for very large releases had been ordered, their installation was incomplete.
The tour looked at the subcooling monitor and the back panel monitor displays, including the in-core thermocouple display (PGaE stated that they were in the process of getting a Westinghouse microprocessor),
the PDO system for acquiring information on seismic ac'celerations, and the reactor vessel level monitor.
After a brief lunch, the tour looked at the remote hot shutdown panel.
John Hoch explained that because many of the cables from this panel run through the cable spreading
- room, PG&E had had to install dedicated instrumentation.
This enabl,es..the plant., t;o..be shutdown. from the, panel,. in.conj.unction
. with local plant actions, even if there is a fire in the cable spreading room.
The group then went through the safeguard switchgear room, the battery and inverter rooms, saw the reactor protective system scram breakers, and walked through the cable spreading room.
John Hoch pointed out that cables were being laid in conduit on the floor of the cable spreading room.
The extra cabling was required to support modifications required ater TMl.
The group visited the fuel handling building; only Commissioner Gilinsky, Edward Abbott, Glenn Kelly, Marvin Mendonca and John Hoch entered the fuel storage area.
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The tour then returned to the control room for a demonstrat'he thermocouple printout system.
The operator explained a ion that a full map of the core could be printed out in fifteen minutes.
A short-form map would take two to three minutes to print out.
Xndividual thermocouple readings can also be retrieved.
After leaving the control room, the tour went outside the reactor building to look at the water storage tanks.
The tour reentered the building to look at the containment purge valves.
PG&E's representatives mentioned that the company was negotiating with the NRC staff to obtain permission to looked open the valves for more than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> per year.
Th
.e. group ed at the fire pumps and fire protection system, a 48-inch butterfly valve',
and the auxiliary feedwater pumps.
The tour also looked at the seismic monitoring system which is intended to monitor the physical behavior of the lant the event of a o
an earthquake.
PG&E's representatives explained that sensors were located throughout the plant and at. three outside locations.
The tour saw one such sensor at the base of the containment.
While at the base of the co t con ainmen e
our also looked at the radwater Sampling Room.
PG&E's personnel explained that pressurized and unpressurized samples could be taken.
The tour then looked at the safety injection pumps, the auxiliary building control board panel, the charging
- pumps, the boron injection tank, and the residual heat removal pump.
On the way to the Unit 1 containment, PG&E's representatives pointed out the 10%,
35%,
and 100% atmospheric steam dump valves.
Nhile inside the Unit 1 containment, the group looked at the pressurizer, the PORVi the recirculation
- sump, the bottom of the containment, the pressurizer relief tank, the in-core
- flux monitoring tubes (including their point of entry into the reactor vessel)',
the reactor coolant
- pumps, and the con a'ottom of a steam. generator.
After leavin th U 't 1
t inment building, the group walked to a point above the salt-water intake structure.
The PG&E representatives pointed out where the breakwater had been',destroyed during'e January
-1981 'storm.(noting that this was not a safety structure) and the location of the screen wash s t d
salt water ter pumps.
The PG&E representatives explained that the salt-water pumps were located in a sealed cavity within the intake structure.
The tour ended at approximately 4:30 p.m.
cc:
Commissioner Gilinsky