ML16342A421
ML16342A421 | |
Person / Time | |
---|---|
Site: | Diablo Canyon |
Issue date: | 02/15/1994 |
From: | Peterson S Office of Nuclear Reactor Regulation |
To: | Office of Nuclear Reactor Regulation |
References | |
NUDOCS 9402280145 | |
Download: ML16342A421 (68) | |
Text
UNITED STATES N
CLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-000I Docket Nos.
50-275 and 50-323 February 15, 1994 LICENSEE:
Pacific Gas and Electric Company (PGKE)
FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2
SUBJECT:
SUNNRY OF JANUARY 12,
- 1994, PUBLIC HEETING TO DISCUSS THE LICENSEE'S PROPOSED TECHNICAL SPECIFICATION AMENDMENT REGARDING COOLING FLOW TO THE CONTAINMENT FAN COOLER UNITS On January 12, 1994, the NRC staff met with the Pacific Gas and Electric Company (PGSE or the licensee) in Rockville, Maryland to discuss the issue stated above.
A list of the attendees present at the meeting is enclosed.
A copy of the licensee's presentation slides is also enclosed.
The licensee presented information on a proposed license amendment request (LAR 94-01) that PG&E submitted to the staff on January 10, 1994.
The changes proposed in LAR 94-01 expand the applicability of the high-high containment pressure signal, revise the flow requirements for the component cooling water system flow requirements in Node 4, clarify the acceptability of ASIDE Section XI testing in Modes 1 through 4, and correct errors in the TS identified during preparation of the LAR.
The licensee discussed the following changes:
TS 3.3.2, "Engineered Safety Features Actuation System," Table 3.3-3 and Table 4.3-2, Functional Units 2.c.
and 3.b.3),
would be revised to expand the mode applicability to include Mode 4.
TS 3/4.6.2.3, "Containment Cooling System,"
would be revised as follows:
1.
would be revised to require that at least four containment fan cooling units (CFCUs), or three
- CFCUs, each supplied by a separate vital bus, be operable.
2.
Action statement
- a. would be revised to clarify the equipment required to be operable when in the action statement.
3.
Action statement
- b. would be deleted.
4.
Action statement
- c. would be renumbered to action statement b.
and revised to clarify the equipment required to be operable when in the action statement.
5.
TS 4.6.2.3a.2) would be revised to clarify the minimum component cooling water (CCW) flow to the CFCUs as 1650 gpm during normal operation which will assure that the required accident flow is satisfied.
9402280145 940215 PDR ADOCK 05000275 P
~~
6.
A footnote would be added to the surveillance requirement of TS 4.6.2.3a.2) allowing all CFCUs to have low CCM flow for ASME Section XI testing and Mode 4 operation with the residual heat removal (RHR) heat exchangers in service for decay heat removal.
7.
TS 4.6.2.3a.3) would be revised to remove cycle specific information that is no longer applicable.
The Bases for TS 3/4.6.2.3 would also be appropriately revised.
The licensee noted that further discussion of the issues discussed in LAR 94-01 is included in Licensee Event Report (LER) 1-93-010.
In order to allow for Mode 4 entry during the next unit refueling outage, PGEE requested that a license amendment be approved by March 1, 1994.
The staff agreed to the schedule and did not see the need for any additional information to review the amendment request.
Enclosure:
- 1. List of Attendees
- 2. Presentation Slides Sheri R. Peterson, Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc w/enclosure:
See next page
0 C
6.
A footnote would be added to the surveillance requirement of TS 4.6.2.3a.2) allowing all CFCUs to have low CCW flow for ASHE Section XI testing and Mode 4 operation with the residual heat removal (RHR) heat exchangers in service for decay heat removal.
7.
TS 4.6.2.3a.3) would be revised to remove cycle specific information that is no longer applicable.
The Bases for TS 3/4.6.2.3 would also be appropriately revised.
The licensee noted that further discussion of the issues discussed in LAR 94-01 is included in Licensee Event Report (LER) 1-93-010.
In order to allow for Mode 4 entry during the next unit refueling outage, PG&E requested that a license amendment be approved by March 1, 1994.
The staff agreed to the schedule and did not see the need for any additional information to review the amendment request.
Enclosure:
- 1. List of Attendees
- 2. Presentation Slides cc w/enclosure:
See next page DISTRIBUTION:
gDocket-File j PDV Reading File NRC
& Local PDRs
- JRoe, 12G18 S.
Peterson EAdensam KPer kins, RV EBarnhill
- EJordan, HNBB3701 ACRS (10),
P315 JMitchell, 17G21
- JWermiel, 8D24
- JDoutt, 8D24
- JHauck, 8D24
- JStewart, 8D24
- PLoeser, 8D24 THurley/FHiraglia, 12G18 Sheri R. Peterson, Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation OFFICE PDV LA EBarnhill PDV PH SPeterson D
PDV Tgua 0 94 2, 7 94 DATE OFFICIAL RECORD COPY DOCUMENT NAME:
DCHTG1.SUH
(
0 t
I
'I
'r. Gregory H.
Rueg
~
Pacific Gas and Electric Co'mpany Diablo Canyon CC:
NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P. 0.
Box 369 Avila Beach, California 93424 Dr. Richard Ferguson, Energy Chair Sierra Club California 6715 Rocky Canyon Creston, California 93432 Hs.
Nancy Culver San Luis Obispo Hothers for Peace P. 0.
Box 164 Pismo Beach, California 93448 Hs. Jacquelyn C. Wheeler 3303 Barranca Court San Luis Obispo, California 93401 Hanaging Editor The County Telegram Tribune 1321 Johnson Avenue P. 0.
Box 112 San Luis Obispo, California 93406 Chairman San Luis Obispo County Board of Supervisors Room 370 County Government Center San Luis Obispo, California 93408 Hr. Truman Burns Mr. Robert Kinosian California Public Utilities Commission 505 Van Ness, Rm.
4102 San Francisco, California 94102 Hr. Steve Hsu Radiologic Health Branch State Department of Health Services Post Office Box 942732 Sacramento, California 94234 Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Haria Lane, Suite 210 Walnut Creek, California 94596 Hr. Peter H. Kaufman Deputy Attorney General State of California 110 West A Street, Suite 700 San Diego, California 92101 Christopher J. Warner, Esq.
Pacific Gas 8 Electric Company Post Office Box 7442 San Francisco, California 94120 Hr. John Townsend Vice President and Plant Hanager Diablo Canyon Power Plant P. 0.
Box 56 Avila Beach, California 93424 Diablo Canyon Independent Safety Committee ATTN:
Robert R. Wellington, Esq.
Legal Counsel 857 Cass Street, Suite D
Honterey, California 93940
ENCLOSURE 1
JANUARY 1
994
~TT N~DS G
TW N TN C
S A F ND G&
SCUSS A 9-Jim Sexton Terence Grebel Pat Nugent Jeff Kelly Rich Clark Jagtar Narula Robert Jakub Jeffrey Bass Sheri Peterson Steven Jones Bill LeFave RGAN 0
PG&E PG&E PG&E PG&E PG&E Westinghouse Westinghouse Westinghouse NRC/NRR/DRPW NRC/NRR/DSSA NRC/NRR/DSSA
SYSTEM OESIGN
~
CCW System 3
CCW Pumps 2 Vital Headers One Non-Vital Header 2
CCW Heat Exchangers Non-Vital Header Isolates During LOCA 8:XREOCOMKHOXCFCU)
l 0
h
SYSTEM OESlGN
~
3 Electrical Busses Vital Busses F, 6 and H
8:XREOGOMKHOKGFGU2
0 I
N
SYSTEM OESIGN
~
5 CFCUs 2
CFCUs on Bus F
2 CFCUs on Bus G
1 CFCU on Bus H
Cooled by Vital CCW s:xREecoMxHescFcu3
DESIGN BASIS CONTAINMENTPRESSURE
~
FSAR Section 6.2B.3 and SSER 16 LOCA Failure of One Vital Bus
{Bus G)
Non-Vital CCW Header Isolates 2
CFCU Operable 2000 gpm CCW Flow to Each CFCU All ECCS Conservatively Assumed to Operate S:XREOGOMXHGXCFCU4
DES/GN GAS/S CCW TEMPERATURE
~
FSAR Section 9.2.2 LOCA Failure of One ASW Pump All Other Equipment Functions as Designed Temperature Cannot Exceed 132 F
Temperature Cannot Exceed 120 F for more than 20 Minutes High CCW Flow Condition (LER 1-93-001)
S:XREGCOMKHGKCFGU6
TS 9.6.2.3 CONTAINMENT COOLING SYSTEM
~
Requires at Least 3
CFCUs Operable During Normal Operations Assures 2 Operable During Accident
~
Currently Requires 2000 gpm CCW Flow to Each CFCU
~
Applicable in Modes 1
through 4
S:XREOCOMXHOXCFCU6
FLOW BALANCE
~
PGKE Developed Flow Balance to Assure 2QQQ gpm During Containment DBA (Bus G Failure)
CCW Flow to CFCUs does not Cause Overheating Adequate CCW Flow Achieved for all Non-Limiting Transients 3:XREGCOMKHOXCFCU20
FLOW BALANCE
~
Flow Balance Methodology 2000 gpm Achieved with Equipment Available Following Bus G Failure Flow Limited to
< 2500 gpm Assuming 3
CCW Pumps and C-Header Isolated CCW Flow Calculated for Non-Limiting Transients Mechanistically 8:KREGCOMKHOXGFCU2$
I l
FLOW BALANCE LOCA
~
Verified that the Mechanistic Failures Resulted in Pressures Lower than the Non-Mechanistic Analysis Analyzed Failures of Busses F,G, and H
Equipment Powered by Failed Bus Assumed to Fail 1600 gpm CCW Flow for all Three Cases Conservatively Used S:KREOGOMKHOXCFCU9
1 S'
FLOW BALANCE MSLB
~
Effect of Flow Balance on Limiting MSLB Limiting Single failure of MFRV/MSIV 3
CFCUs Operable 2 Containment Spray Trains Operable SAREGCOMXHGXCFCU)2
I
FLOW BALANCE MSLB
~
Evaluation of non-limiting bus failure 1600 CCW flow to CFCUs 2
CFCUs operable Determined that Flow Change was Insignificant Due to Margin Available s:iREecoMaHexcFcu<3
k
CON TAINMENTCOOLING RHR HX OPERATION
~
Determined Expected Flow to CFCUs with RHR HXs in Service
~
Analyzed Acceptability of Flow During Mode 4iSection XI Testing
~
Single Failure Not Considered Due to Limited Duration of Under Footnote
~
Sufficient Containment Cooling is Available to Mitigate all Mode 1
Accidents
0 x
REVISED CFCU TS 3/4.6.2.3 AND CONTAINMENT HIGH-HIGH PRESSURE SIGNAL TS 3/4.3.2 S:KREGCOMXHOXPTN)
'I
~
V I
DESCRIPTION OF AMENDMENT TS 3/4.6.2.3 CONTAINMENTCOOLING SYSTEM
~
Revise Minimum CCW Flow Surveillance Requirements from 2000 to 1 650 gpm
~
Delete Action Statement b.
~
Add Footnote to Allow for RHR HX Operation in Mode 4 and Section Xl Testing
~
Clarify Equipment Requirements
~
Majority of Changes Specific to Diablo Canyon 8:XREOCOMXHOKPTN2
a
DESCRlPTllON OF AMENOMENT TS 3/4.3.2
~
Revise Mode Applicability for Containment High-High Pressure Signal S:KREOCOMXHGKPTN3
BACKGROUND CHRONOLOGY
~
Comprehensive Review of CCW System
- Design, Operation, and Surveillance Requirements
~
Potential Overheating of CCW System LER 1-93-001
~
Implemented New Flow Balance
~
Low Flow Conditions to CFCUs with RHR HXs in Service LER 1-93-010 SAREOCOMXHOXPTN4
BACKGROUND CONTAINMENTDESIGN BASIS
~
~
Failure to Vital Bus 6 2 CFCUs Operable with 2000 gpm CCW Flow 1
Containment Spray Train Operable Non-vital CCW Header Isolated
~
All ECCS Pumps Assumed to Function SAREGCOMXHGKPTN6
BACKGROUND CCW TEMPERATURE DESIGN BASIS
~
~
Failure of 1
ASW Pump
~
All CCW Components Operate as Designed
~
All CFCUs Operate as Designed S:XREOCOMXHOXPTN6
1
BACKGROLIND FLOW BALANCE
~
Assures that at Least 2000 gpm CCW Flow to CFCUs During DBA
~
Assures that CCW System will not be Overheated
~
Results in Less than 2000 gpm Indicated Flow During Normal Operation Assures Adequate CCW Flow During all Other Accidents S:XREOCOMKHOXPTN7
JUSTIFICATION TS 3/4.6.2.3 CONTAINMENTCOOLING SYSTEM
~
Clarifies CCW Flow Requirements for CFCUs
~
Clarifies Acceptability of Section XI Testing
~
Clarifies Acceptability of Mode 4 Operation
~
Deletes an Unsupported Action Statement
~
Clarifies Acceptable Equipment Configurations SAREOCOMXHOXPTN8
k
JUS TIFICATION TS 3/4.3.2 HIGH-HIGH CONTAINMENTSPRAY 5.
~
Conservative Change to Assure that Assumptions for Mode 1
Analysis Satisfied in Mode 4
~
Assures Isolation of CCW Non-vital Header
~
Assures Actuation of Containment Spray SAREOCOMXHOXPTN9
SAFETY EVALUATION
~
1600 GPM During Normal Operation Satisfies DBA Heat Removal Requirements 3 CFCUs Supply Adequate Heat Removal During Mode 4
RHR HX Operation and Section XI Testing
~
Other Changes Clarify TS and/or are Conservative SAREOCOMKHOKPTN10
fl
Bocket Nos.
50-275 and 50-323 February 4, LICENSEE:
Pacific Gas and Electric Company (PG&E)
FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF JANUARY 12,
- 1994, PUBLIC MEETING TO DISCUSS THE LICENSEE'S PARTIAL IMPLEMENTATION OF THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS On January 12, 1994, the NRC staff met with the Pacific Gas and Electric Company (PG&E or the licensee) in Rockville, Maryland to discuss the issue stated above.
A list of the attendees present at the meeting is enclosed.
The l.icensee briefly discussed its intentions to implement NUREG 1366 on reduced surveillance requirements for testing during power operations.
The licensee also discussed plans to implement portions of the improved standard technical specifications (ISTS) including the split report that allows the relocation of certain technical specifications (TS) to licensee controlled procedures.
The licensee's controls for relocated TS were also discussed and the staff stated that 10 CFR 50.59 should be applied to those TS that have been relocated.
The staff also noted that adopting the split report is considered a prelude to a complete conversion to the ISTS and the licensee clearly stated that they do not intend to convert to the ISTS at this time due to the resources involved in such an effort.
The staff briefly discussed the status of the technical specification improvement program with regard to managing complete conversions to the ISTS and the line-item improvement process.
The licensee asked the staff about providing recent revisions to the ISTS on the existing electronic bulletin board system that currently allows the licensee to access Revision 0 of the ISTS dated September 1992.
The staff responded that the latest revisions made to the ISTS are not on the bulletin board system,
- however, the revisions are accessible through the Owner's Groups.
Original signed by:
Sheri R. Peterson, Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office.of Nuclear Reactor Regulation
Enclosure:
List of Attendees cc w/enclosure:
See next page
~OIB IBO ION:
t-Docket:Fi.l'e PDV Reading File S.
Peterson EAdensam
- EJordan, MNBB3701 ACRS (10),
P315
- JDoutt, 8D24
- JMauck, 8D24 TMurley/FMiraglia, 12G18 OBOE c;m NRC & Local PDRs
- JRoe, 12G18
- KPerkins, RV EBarnhill JMitchell, 17G21
- JWermiel, 8D24
- JStewart, 8D24
I /94 DATE
/
/94 OFFICIAL RECORD COPY DOCUMENT NAME:
DCTSNTG.SUM D
PDV T ua
/94
Docket Nos. 50-275 and 50-323 February 4,
4 LICENSEE:
Pacific Gas and Electric Company (PG&E)
FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2
SUBJECT:
SUMHARY OF JANUARY 12,
- 1994, PUBLIC MEETING TO DISCUSS THE LICENSEE'S PARTIAL IMPLEMENTATION OF THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS On January 12, 1994, the NRC staff met with the Pacific Gas and Electric Company (PG&E or the licensee) in Rockville, Maryland to discuss the issue stated above.
A list of the attendees present at the meeting is enclosed.
The licensee briefly discussed its intentions to implement NUREG 1366 on reduced surveillance requirements for testing during power operations.
The licensee also discussed plans to implement portions of the improved standard technical specifications (ISTS) including the split report that allows the relocation of certain technical specifications (TS) to licensee controlled procedures.
The licensee's controls for relocated TS were also discussed and the staff stated that 10 CFR 50.59 should be applied to those TS that have been relocated.
The staff also noted that adopting the split report is considered a prelude to a complete conversion to the ISTS and the licensee clearly stated that they do not intend to convert to the ISTS at this time due to the resources involved in such an effort.
The staff briefly discussed the status of the technical specification improvement program with regard to managing complete conversions to the ISTS and the line-item improvement process.
The licensee asked the staff about providing recent revisions to the ISTS on the existing electronic bulletin board system that currently allows the licensee to access Revision 0 of the ISTS dated September 1992.
The staff responded that the latest revisions made to the ISTS are not on the bulletin board system,
- however, the revisions are accessible through the Owner's Groups.
Original signed by:
Sheri R. Peterson, Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
List of Attendees cc w/enclosure:
See next page DISTRIBUTION:
Docket File PDV Reading File NRC & Local PDRs
- JRoe, 12G18 S.
Peterson EAdensam
- KPerkins, RV EBarnhil 1
- EJordan, MNBB3701 ACRS (10),
P315 JMitchell, 17G21
- JWermiel, 8D24
- JDoutt, 8D24
- JMauck, 8D24
- JStewart, 8D24
- PLoeser, 8D24 TMurley/FMiraglia, 12G18 PDV LA PDV PH OFFICE EBarnhfll SS NAME SPetersorf 2/
I /94
/
/94 DATE OFFICIAL RECORD COPY DOCUMENT NAME:
DCTSMTG.SUH D
PDV T ua
/94
0
Mr. Gregory M. Rueg~
Pacific Gas and Ele'PSFic Company Diablo Can CC; NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P. 0.
Box 369 Avila Beach, California 93424 Dr. Richard Ferguson, Energy Chair Sierra Club California 6715 Rocky Canyon Creston, California 93432 Ms. Nancy Culver San Luis Obispo Mothers for Peace P. 0.
Box 164 Pismo Beach, California 93448 Ms. Jacquelyn C. Wheeler 3303 Barranca Court San Luis Obispo, California 93401 Managing Editor The County Telegram Tribune 1321 Johnson Avenue P. 0.
Box 112 San Luis Obispo, California 93406 Chairman San Luis Obispo County Board of Supervisors Room 370 County Government Center San Luis Obispo, California 93408 Mr. Truman Burns Mr. Robert Kinosian California Public Utilities Commission 505 Van Ness, Rm.
4102 San Francisco, California 94102 Diablo Canyon Independent Safety Committee ATTN:
Robert R. Wellington, Esq.
Legal Counsel 857 Cass Street, Suite D
Monterey, California 93940 Mr. Steve Hsu Radiologic Health Branch State Department of Health Services Post Office Box 942732 Sacramento, California 94234 Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Peter H. Kaufman Deputy Attorney General State of California 110 West A Street, Suite 700 San Diego, California 92101 Christopher J. Warner, Esq.
Pacific Gas
& Electric Company Post Office Box 7442 San Francisco, California 94120 Mr. John Townsend Vice President and Plant Manager Diablo Canyon Power Plant P. 0.
Box 56 Avila Beach, California 93424
ENCLOSURE 1
AME ATTENDEES JANUARY 12 1994 MEETING BETMEEN NRC STAFF AND PG&E 0
D SCUSS FUTURE CHA GES 0 THE IAB 0 C
0 ECHNICAL SPECIFIC TIONS OG ON Jim Sexton Terence Grebel Chris Grimes Sheri Peterson Pat Nugent James Raleigh PG&E PG&E NRC/NRR/OTSB NRC/NRR/PDV PG&E Southern Technical Services
~ (
t
Docket Nos.
50-275 and 50-323 February 4, 4
LICENSEE:
Pacific Gas and Electric Company (PGSE)
FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF JANUARY 12,
- 1994, PUBLIC MEETING TO DISCUSS THE LICENSEE'S PARTIAL IMPLEMENTATION OF THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS On January 12, 1994, the NRC staff met with the Pacific Gas and Electric Company (PG&E or the licensee) in Rockville, Maryland to discuss the issue stated above.
A list of the attendees present at the meeting is enclosed.
The licensee briefly discussed its intentions to implement NUREG 1366 on reduced surveillance requirements for testing during power operations.
The licensee also discussed plans to implement portions of the improved standard technical specifications (ISTS) including the split report that allows the relocation of certain technical specifications (TS) to licensee controlled procedures.
The licensee's controls for relocated TS were also discussed and the staff stated that 10 CFR 50.59 should be applied to those TS that have been relocated.
The staff also noted that adopting the split report is considered a prelude to a complete conversion to the ISTS and the licensee clearly stated that they do not intend to convert to the ISTS at this time due to the resources involved in such an effort.
The staff briefly discussed the status of the technical specification improvement program with regard to managing complete conversions to the ISTS and the line-item improvement process.
The licensee asked the staff about providing recent revisions to the ISTS on the existing electronic bulletin board system that currently allows the licensee to access Revision 0 of the ISTS dated September 1992.
The staff responded that the latest revisions made to thd ISTS are not on the bulletin board system,
- however, the revisions are accessible through the Owner's Groups.
Original signed by:
Sheri R. Peterson, Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
List of Attendees cc w/enclosure:
See next page
~OIRTRIOOTIO Docket File PDV Reading File S. Peterson EAdensam
- EJordan, MNBB3701 ACRS (10),
P315
- JDoutt, 8D24
- JMauck, 8D24 THurley/FMiraglia, 12G18 NRC & Local PDRs
- JRoe, 12G18
- KPerkins, RV EBarnhill JHitchell, 17G21
- JWermiel, 8D24
- JStewart, 8D24
- PLoeser, 8D24 OFFICE PDV LA PDV PN EBarnh111 SS NAME SPetersorf
// /94 2,/ "I 94 DATE OFFICIAL RECORD COPY DOCUMENT NAME:
DCTSNTG.SUN D PDV T ua
/94
1
Hr. Gregory M. Rueg~
Pacific Gas and Ele~ic Company Diablo Can Cco NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P. 0.
Box 369 Avila Beach, California 93424 Dr. Richard Ferguson, Energy Chair Sierra Club California 6715 Rocky Canyon Creston, California 93432 Hs.
Nancy Culver San Luis Obispo Mothers for Peace P. 0.
Box 164 Pismo Beach, California 93448 Hs. Jacquelyn C. Wheeler 3303 Barranca Court San Luis Obispo, California 93401 Hanaging Editor The County Telegram Tribune 1321 Johnson Avenue P. 0.
Box 112 San Luis Obispo, California 93406 Chairman San Luis Obispo County Board of Supervisors Room 370 County Government Center San Luis Obispo, California 93408 Hr. Truman Burns Hr. Robert Kinosian California Public Utilities Commission 505 Van Ness, Rm. 4102 San Francisco, California 94102 Mr. Steve Hsu Radiologic Health Branch State Department of Health Services Post Office Box 942732 Sacramento, California 94234 Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Hr. Peter H. Kaufman Deputy Attorney General State of California 110 West A Street, Suite 700 San Diego, California 92101 Christopher J. Warner, Esq.
Pacific Gas
& Electric Company Post Office Box 7442 San Francisco, California 94120 Hr. John Townsend Vice President and Plant Manager Diablo Canyon Power Plant P. 0.
Box 56 Avila Beach, California 93424 Diablo Canyon Independent Safety Committee ATTN:
Robert R. Wellington, Esq.
Legal Counsel 857 Cass Street, Suite D
Monterey, California 93940
I
i g)
ENCLOSURE 1
NAME TTENDEES JANUARY 12 1994 EETING BETWEEN E
N C
S A
ND G&E 0 DISCUSS FUTU CH NG S
0 E
B 0 C
0 C
IC S
CI ICATIONS 0
G 0
Jim Sexton Terence Grebel Chris Grimes Sheri Peterso'n Pat Nugent James Raleigh PG&E PG&E NRC/NRR/OTSB NRC/NRR/PDV PG&E Southern Technical Services
~
1
. ~