ML20045D621
| ML20045D621 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/24/1993 |
| From: | Brown S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-M86377, NUDOCS 9306290233 | |
| Download: ML20045D621 (25) | |
Text
,
June 24, 1993 Docket No. 50-206 LICENSEE: Southern California Edison Company (SCE)
FACILITY:
San Onofre Nuclear Generating Station, Unit 1.(SONGS 1)
SUBJECT:
SUNiARY OF MEETING HELD ON JUNE 18, 1993, TO DISCUSS PROPOSED PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS (PDTS) FOR SONGS 1 (TAC NO. M86377)
On June 18, 1993, NRC staff members met at Rockville, Maryland, with employees of SCE to discuss the proposed PDTS for SONGS 1.
A list of attendees is included as enclosure 1.
The handout used by SCE at the meeting is included as enclosure 2.
SONGS 1 was permanently shut down on November 30, 1992, and its Possession Only License became effective on March 9, 1993. The reactor is defueled and all fuel has been transferred to the spent fuel pool.
SCE proposed to replace SONGS 1 Technical Specifications with PDTS to eliminate unnecessary specifications and surveillance requirements for SONGS 1.
Further, SCE requested that the staff approve the PDTS amendment request by late August 1993 in order for "E to avoid the high cost of certain required emergency diesel surveillancet Original signed by:
Stewart W. Brown, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
1.
Meeting Attendees 2.
Meeting Handout cc w/ enclosures:
See next page DISTRIBUTION:[SONGMT.SWB] (Brown-lb disk) iDocket Files R. Dudley PDRs S. Brown ONDD R/F OGC DORS R/F E. Jordan T. Murley/F. Miraglia NRC Participants J. Partlow ACRS (10)
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WASHINGTON, D.C. 2055 % 0001 June 24, 1993 Docket No. 50-206 LICENSEE: Southern California Edison Company (SCE)
FACILITY:
San Onofre Nuclear Generating Station, Unit 1 (SONGS 1)
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 18, 1993, TO DISCUSS PROPOSED PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS (PDTS) FOR SONGS 1 (TAC NO. M86377)
On June 18, 1993, NRC staff members met at Rockville, Maryland,.with employees of SCE to discuss the proposed PDTS for SONGS 1.
A list of attendees is included as enclosure 1.
The handout used by SCE at the meeting is included as enclosure 2.
SONGS I was permanently shut down on November 30, 1992, and its Possession Only License became effective on March 9,1993. The reactor is defueled and all fuel has been transferred to the spent fuel pool. SCE-proposed to replace SONGS 1 Technical Specifications with PDTS to eliminate unnecessary specifications and surveillance requirements for SONGS 1.
Further, SCE requested that the staff approve the PDTS amendment request by late August 1993 in order for SCE to avoid the high cost of certain required emergency diesel surveillances.
<>s+ l h MW Stewart W. Brown, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
1.
Meeting Attendees 2.
Meeting Handout cc w/ enclosures:
3 See next page l
~.
Mr. Harold B. Ray San Onofre Nuclear Generating Southern California Edison Company Station, Unit 1 Docket No. 50-206 cc:
Mr. R. W. Krieger, Station Manager Southern California Edison Company San Onofre Nuclear Generating Station P. O. Box 128 San Clemente, California 92674-0128
-i Mr. Robert G. Lacy Manager, Nuclear Department San Diego Gas & Electric _ Company P. O. Box 1831 San Diego, California 92112 Resident Inspector / San Onofre NPS c/o U.S. Nuclear Regulatory Commission P. O. Box 4320 San Clemente, California 92674 Mayor City of San Clemente 100 Avenida Presidio San Clemente, California 92672 Chairman, Board of Supervisors County of San Diego 1600 Pacific Highway, Room 335 San Diego, California 92101 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Steve Shu Radiologic Health Branch State Department of Health Services P. O. Box 942732 Sacramento, California 94234 Mr. Don J. Womeldorf Chief, Environmental Management Branch i
California Department of Health Services s
714 P. Street, Room 616 Sacramento, California 95814 Mr. Richard J. Kosiba, Project Manager Bechtel Power Corporation 12440 E. Imperial Highway Norwalk, California 90650
ENCLOSURE 1 June 18. 1993 Southern California Edison Meetino 1.ist of Attendees Stewart Brown NRR/ DORS /0NDD Kevin Graney SERCH/ Licensing Bechtel Jim Shepherd NMSS/LLWM/LLDR Walter C. Marsh SCE E. Scott Medling SCE J. Steven Nunez SCE' Richard Dudley NRR/ DORS /0NDD Michael Webb NRR/00RS/0NDD b
e
ENCIDSURE 2
.i SONGS 1 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS b
o 5
ROCKVILLE, MARYLAND i
4 I
I JUNE 18,1993
DISCUSSION TOPIC _S i
e Overview e
Summarize. Permanently Defueled Technical Specifications (PDTS)
Regulatory Based (10 CFR 50.36)
Safety Limits Limiting Conditions for Operation Surveillances e
Present PDTS safety analysis e
Describe administrative controis to be implernented concurrently with PDTS e
Address NRC identified topics to be. considered.
for inclusion in PDTS 9
V 1
Spent Fuel Pool Water Temperature During Loss of Forced Cooling Spent Fuel Pool Water Temperature ( F)
Boiling Not Credible (Passive Cooling) 200 -
180*F Equilibrium Temperature w/o Forced Cooiling Analysis (8/93) 150 -
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PreliminaryTest i
Data (5/93) j l
100 -
- ,9 9
sip #
50 0
'1 2
3 4
5 6
Time After Loss of Cooling (Days) t i
,,.-v
,e <
b Spent Fuel Pool Water Level During Loss of Forced Cooling (no water addition)
Spent Fuel Pool Water Level (Plant Elevation, Feet) 45 -
Preliminary Test Data (5/93)
Proposed Limiting Condition for Operation,40'3" '
40 35 -
s Analysis (8/93) 30 -
10* Above Stored Fuel
- - - - - - - - - - - - - - - (SRP 9.1.3 Siphon / Leak Limit) 25 -
20 -
Proposed Safety Limit 16' 15 -:::: :::::::::::::::::::::::::::::::::::::::::::::::::::::::::::- ::- -- : :___
Top cf Stored Fuel,15'1" 10 -
5-0 0
10 20 30
- 40 Time After Loss of Cooling (Days)
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TECHNICAL SPECIFICATIONS CONTENT AND PURPOSE (10 CFR 50.36) e Safety limits... process variable restrictions to protect physical barriers that guard against uncontrolled radioactivity release e
Limiting conditions for operation... lowest equipment performance levels for safe facility operation e
Surveillance requirements... maintain quality of systems / components so facility operation within safety limits and limiting conditions of operation
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SAFETY LIMIT i
e SAFETY LIMIT - - Maintain spent ' fuel pool (SFP).
1 water level above stored fuel to preclude fuel' overheating i
e Fuel storage facility inherently safe during i
permanently defueled condition
x..
f SAFETY ANALYSIS a
e Fuel storage facility design previously-accepted NRC SER,12/7/82 NRC SER,7/11/86 NRC SER,7/16/90
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e Unit 1 Design Basis Accidents Loss of offsite power / blackout Fuel handling accident e
Control room habitability SONGS 1 accidents, OK SONGS 2/3 severe accidents, evacuate h '
l
SAFETY ANALYSIS-LOSS OF OFFSITE POWER e
Potential safety consequences... loss of SFP cooling i
e Low SFP heat load Adequate time to restore power / cooling Passive cooling (open building doors for-extended LOP conditions)
Sufficient makeup water available through gravity feed,5 days minimum e
Acceptable radiological consequences 10 CFR 100 satisfied 10 CFR 20 satisfied e
SFP cooling and support systems not essential for safe fuel storage 4
Spent Fuel Pool Heat Load During Permanently Defueled Condition Spent Fuel Pool Heat Load (MBtu/hr)
Maximum Abnormal Heat load (17 MBlu/hr) 17 - - - - - - - - - -
16 -
15 -
14 -
13 -
12 -
11 -
10 -
9-8-
7-Maximum Normal Heat Lcad (6.5 MBlu/hr) 6-5-
4-t 3-l 2-l I
Defueling Completed 1-i 0
3/1/93 3/1/94 3/1/95 3/1/96 3/1/97 Calendar Date
Spent Fuel Pool Equilibrium Temperature and Maximum Evaporation Rate (no forced cooling, open fuel storage building rollup and personnel access doors)
Maximum Spent Fuel Pool Spent Fuel Pool Equilibnum Evaporation
- Temperature (*F)
Rate (gpm) 210 -
-9 k
200 -
-8
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190 - !%
-7 180 -l-- g---
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8
- "#' '"'* I 170 -
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-5 160 - l
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_4 150- l l%
i 140 - l l
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""* enn, 130 - i
-2 l
- "* een ens,
- * =
Evaporation Rate (gpm) l 120 -
-1 110 - l Defueling completed on 3/6/93, 0
100-i 3/1/93 8/29/93 3/1/94 3/1/95 3/1/96 3/1/97 Calendar Date v
Time for Spent Fuel Pool Temperature to Reach 150 F After Loss of Cooling (no spent fuel pool heat loss )
Time (Hours) 100_
90 _
80 _
70 -
60 _
50 _
40 -
30 -
20 -
l l
10 -
l Defueling Completed i
on 3/6/93 0
i i
i 9/1/93 12/1/93 3/1/93 6/1/93 Caiendar Date
SAFETY ANALYSIS FUEL HANDLING ACCIDENT e
improved SFP shutdown margin SFP maximum K n = 0.896 e
(< 0.95 acceptance criteria)
K n calculated assuming no SFP boration e
and storage of fresh fuel Reduced K for defueled condition...
ey spent fuel less reactive than fresh fuel e
Reduced radiological consequences e
SFP load handling limit
, T
- 7
}n SAFETY ANALYSIS - FUEL HANDLING ACCIDENT l
1
. Assumed Thyroid Dose Condition Accident Occurrence *
(Exclusion Area Boundary) j Current Licensing Basis 148 Hours 99 rem (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
Defueled Condition 110 Days 0.015 rem (Duration of Release)
- Time after reactor shutdown _ _ _ _ _ _ _ _
4 1
SAFETY ANALYSIS CONTROL ROOM EVACUATION e
Two Certified Fuel Handlers e
Control room evacuation permissible during severe offsite hazards / Unit 2/3 accidents e
Daily monitoring sufficient for brief periods Adequate time to correct equipment malfunctions Minimal SFP evaporation during any 24 3
hour period l
1 l
9 l i
4 LIMITING CONDITIONS ~FOR OPERATION e
SFP water level Plant elevation 40' 3" e
SFP temperature /
< 150 F cooling One train of cooling
- e SFP makeup Auxiliary feedwater storage-tank water level e
SFP water chemistry s 0.15 ppm chloride s 0.15 ppm fluoride e
SFP load handling s 1500 lbs limit t
F Commercial grade except for. portion of system-which is part of SFP pressure boundary.
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ADMINISTRATIVE CONTROLS e
Auxiliary electrical supply e
Control room emergency air treatment system e
Radiation monitors e
SFP water loss 1
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W NRC IDENTIFIED TOPICS TO BE CONSIDERED FOR INCLUSION IN PDTS*
TOPIC INCLUDED COMMENT 1.
Definitions Yes Definitions for systems in PDTS included.
2.
Radiation Monitoring No Control room evacuation permissible.
(Control room and SFP areas) 10 CFR 20 met during LOP conditions.
Maintain radiation rnonitoring for control room and SFP areas as commercial grade.
3.
Seismic Instrumentation No Unit 2/3 provisions for seismic monitoring sufficient for San Onofre site.
4.
Meteorological Instrumentation No Unit 2/3 provisions for meteorological monitoring sufficient for San Onofre site.
5.
Chlorine Detection System No SONGS 1 not equipped with chlorine detection system.
6.
Waste Gas Holdup System No Waste gas holdup system out of service during defueled condition.
- NRC letter to.SCE, October 30,1992.
- 17. -
NRC IDENTIFIED TOPICS TO BE CONSIDERED FOR INCLUSION IN PDTS l
TOPIC INCLUDED COMMENT 7.
Flood Protection No SONGS 1 provisions for flood protection accepted by NRC during Systematic Evaluation Program.
8.
Control Room Emergency No Continuous manning of control room not Air Cleanup System required during severe accidents. Long time available to correct equipment malfunctions.
Maintain commercial grade.
9.
Sealed Source Contamination Yes Existing Technical Specification requirements included.
10.
AC Sources No Auxiliary electrical supply not essential for safe fuel storage. Maintain commercial grade.. -.
NRC IDENTIFIED TOPICS TO BE CONSIDERED FOR INCLUSION IN PDTS TOPIC INCLUDED COMMENT 11.
Onsite Power Distribution No Auxiliary electrical supply not essential for safe fuel storage. Maintain commercial grade.
12.
Water Level Spent Fuel Pool Yes Existing Technical Specification requirement included.
13.
Spent Fuel Storage Air No Existing ventilation systems for the fuel Cleanup System storage facility not required for safe fuel storage. Maintain existing system commercial grade.
14.
Uquid Holdup Tank No Technical Specification for limiting contents of outside liquid storage tanks is not required (NRC Amendment No. 79, 8/27/84).
NRC IDENTIFIED TOPICS TO BE CONSIDERED FOR INCLUSION IN PDTS TOPIC INCLUDED COMMENT 15.
Spent Fuel Pool Yes SFP temperature and cooling requirements Temperature / Cooling System included.
16.
Spent Fuel Pool Water Yes Requirements for chloride and fluoride Chemistry concentrations included to protect against potential corrosion damage.
17.
Spent Fuel Pool Grane Yes Existing Technical Specification limit for loads handled over SFP included.
18.
Component Cooling Water Yes Component cooling water system (CCWS) included in PDTS as part of SFP cooling train.
19.
Service Water System Yes The saltwater cooling system (SWCS) transfers heat from CCWS to Pacific Ocean.
SWCS included in _PDTS as part of SFP cooling train.
e NRC IDENTIFIED TOPICS TO BE CONSIDERED FOR INCLUSION IN PDTS TOPIC INCLUDED COMMENT 20.
Ultimate Heat Sink No SFP cooling function not essential for safe fuel storage. Maintain intake structure commercial grade.
21.
Emergency Diesel Generator No Auxiliary electrical supplies not essential for Support Systems safe fuel storage. Maintain emergency diesel. generators and associated support systems commercial grade until SFP temperature would not exceed 150*F if cooling were lost without restoration.
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SUMMARY
o Proposed PDTS ensure safe facility operation during-defueled condition e-Administrative controls concurrent.with PDTS-C v
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