ML20054E472
| ML20054E472 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 06/07/1982 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-82-029, SLNRC-82-29, NUDOCS 8206110251 | |
| Download: ML20054E472 (8) | |
Text
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SNUPPS Stenderdised Nuclear Unit Power Mont System 5 Choke Cherry Road Nicholas A. Petrick v
land 20850 Executive Director June 7, 1982
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SLNRC 82- 029 FILE:
0278 SUBJ: Status of Callaway and Wolf Creek SER Issues Mr. Harold R. Denton, Director \\
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Connission Washington, D. C.
20555 Docket Nos: STN 50-482 and STN 50-483
Dear Mr. Denton:
Attached is a ~ status report on the outstanding, confirmatory, and license condition 1:,3ues reported in the Callaway and Wolf Creek Safety Evaluation Reports. This report is provided so that the SNUPPS Utilities and the NRC Staff may continue the tim.?ly resolution of safety issues.
If there are any questions on this matter, please contact Mr. R. Stright of the SNUPPS Staff.
Very truly yours, RA4%
Nicholas A. Petrick RLS/mtk l
1 cc:
G. L. Koester KGE D. T. McPhee KCPL D. F. Schnell UE pl T. E. Vandel NRC/WC J. H. Neisler NRC/ CAL l
l 8206110251 820607 PDR ADOCK 05000482 A
PDR l
SLNRC 82 029 Status of Callaway and Wolf Creek SER Issues I.
Outstanding Issues:
--Status / Remarks Issue CAL WC 1
N/A Ice load analysis for A submittal by UE was made by ESW System ULNRC-546, dated 3/2/82.
NRC has the action.
2 B.1 High-energy pipe The SNUPPS FSAR was revised in break hazards analysis Rev. 9 to document the completed analyses. NRC has the action.
3 Vibration damping This issue is resolved. Refer to analysis for cable tray Callaway SSER #1.
and conduit support systems 4
B.2 Pump and valve The NRC must identify any new in-operability assurance formation requirements.
Construction program will support an 8/82 audit at Callaway; first quarter 1983 at Wolf Creek.
5 Pipe support baseplate This issue is resolved.
Refer to flexibility and its Callaway SSER #1.
effect on anchor bolt loads 6
A.1 Seismic and dynamic The first part of the NRC's request qualification of seismic for information was answered by Category I mechanical SLNRC 82-06.
Construction will support and electrical equipment an 8/82 audit at Callaway; first quarter 1983 at Wolf Cree':. NRC action.
7 A.2 Environmental qualifi-The following schedule is planned:
cation of safety-related documentation submittal - 12/82 electrical equipment audit - 02/83.
8 8.4*
Fuel assembly structural This issue is resolved.
A follow-up response to seismic and submittal was made on 12/23/81.
NRC LOCA forces lists as confirmatory #30 in Callaway SSER #1.
9 Level measurement errors This issue is resolved. Refer to due to environmental temp-Callaway SSER #1.
erature effects on level instrument reference legs 10.
B.3 Fire protection programs-The FSAR was revised in Rev. 8 to
. alternate shutdown panel describe design changes.
4/30/82 meeting indicated more work was required for the control room fire analysis.
NRC and SNUPPS action.
11 Systems and components This issue is resolved.
See Wolf Creek on the Q-list SER. A Callaway SSER writeup is required by the NRC.
- !!olf Creek Confirmatory Item
Status of Callaway and Wolf Creek SER Issues Issue Status / Remarks WC CAL
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TMI Action Plan N/A A.3 Shift Technical Advisor NRC action to complete the review of KGE's STA program.
12 B.4 I.C.1: Guidance for evaluation Completed Westinghouse Owners and development of proce-Group guidelines will be sub-dures for transients mitted 7/82. Verification on and accidents the Callaway simulator will be held in 6/82.
12 B.4 I.C.8: Pilot monitoring of See Status of I.C.1 above.
selected emergency procedures for near term operating license applicants 12 A.3 I.D.1: Control room design An interim submittal was made on review 1/19/82.
A meeting with the NRC was held on 2/9/82. Another submittal was made on 4/12/82.
NRC action required. KGE will make a submittal by 6/30/82.
Final resolution unlikely until 3/83.
12 B.4 II.B.2: Plant shielding to provide The completed shielding and access to vital areas and access study will be submitted protect safety equipment for by 7/82.
postaccident operation 12 A.3 III.A.l.2: Upgrade emergency support The NRC has the action on facilities this issue.
13 B.27*
Locked Rotor Information to resolve was provided by SLNRC 82-07.
II. Confirmatory Issues:
1 B.1 Additional seismic instrumen-The FSAR was revised in tation and control room Rev. 8 to document the design indication change.
NRC has the action.
2.
B.2 Analysis of steam generator The analysis and proposed for tube plugging criteria tech specs will be submitted 6/82.
3.
B.3 Testing of pressure isolation The NRC requested informaticq on this valves issue. A response will be provided by by 7/15/82. Proposed tech specs wil be submitted 6/82.
4 Cladding collapse time This issue is closed. Refer to analysis SSER #1.
5 B.5 Preservice inspection The PSI program has been submitted.
testing program No additional submittals are planned.
NRC has the -tion.
oWolf Creek Confirmatory Item T
Status of Callaway and Wolf Creek SER Issues Issue Status / Remarks CAL WC 6
B.6 Steam generator inservice Proposed tech specs will be inspection submitted 6/82.
B.7 ECCS Analysis The SNUPPS FSAR was revised in Rev. 9 to close this issue.
7 8.8 Steam generator level control The SNUPPS FSAR was revised and protection in Rev. 9 to document the design change.
8 B.9 Capability for safe shutdown This issue will be confirmed following loss of a bus supply-after procedures are finalized ing power to instruments and in early 1983.
controls 9
B.10 Operator actions required to The information required to close maintain safe shutdown from this issue was submitted by outside the control room SLNRC 81-111, 9/22/81.
10 B.ll Reactor coolant temperature The FSAR will be revised in 8/82 indicators on the auxiliary to document the design change.
shutdown panel 11 B.12 Volume control tank level The FSAR will be revised 10/82 control and protection inter-to document the desgin change.
action 12 B.13 Boron dilution control The FSAR will be revised in 8/82 to document the design change.
13 B.14 Environmental qualification A submittal will be made in of control systems 8/82 to close this issue.
14 B.15 Circuitry for automatic Drawings are available for transfer of diesel generator NRC review.
from test to auto control mode 15 B.16 Diesel generator reliability Test report is available for qualification testing NRC review.
16 B.17 Circuitry for bypass of The FSAR was revised in Rev. 8 protective circuitry to document the design change.
17 B.18 Circuitry for Inservice Drawings are available for NRC testing per RG 1.108 review.
18 B.19 Low and/or degraded The FSAR was revised in Rev. 7.
grid voltage New dwg. needed for Section 1.7 and will be available about 7/82.
Status of Callaway and Wolf Creek SER Issues Issue Status / Remarks CAL WC 19 B.20 Use of regulating-type A submittal will be made transformer as isolaticn 10/82 to close this issue.
device 20 B.21 Isolation of control room Drawings are available for and remote circuits NRC review.
21 B.22 Sequencing of loads on the Drawings are available for offsite power system NRC review.
22 B.23 Submerged electrical Drawings are available for equipment NRC review.
23 B.24 Separation of cables inside An NRC site visit is suggested panels for 8/82, for Callaway.
24 B.25 Compliance with position 1 The information required to of RG 1.63 close this item will be available for review 8/82.
25 A.6 Fire protection site visit An NRC site visit is suggested for 9/82 for Callaway, Spring
'83 for Wolf Creek.
26 B.26 Monitoring of rocker arm This item will not be closed lube oil system temperature until late in the pre-operational for diesel generators test program, t
27 A.7 Security Plan This issue is closed for Callaway.
Refer to SSER #1. For Wolf Creek;a submittal was made in 4/82, NRC action.
TMI Action Plan
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28 I.G.1: Special low-power Rev. 8 to FSAR included changes testing and training to resolve this issue.
Resolved Y
in Wolf Creek SER. A Callaway SSER writeup is required.
28 B.28 II.D.1: Performance testing of Preliminary evaluation submitted by BWR and PWR relief and SLNRC 82-23.
Final submittal planned safety valves for 12/82.
28 B.28 II.E.1.1: Recommendation GS-2, This issue will be closed just s
physical locking of prior to fuel load.
isolation valve.
28 8.28 II.E.4.2: Containment isolation' A report on purge valve operability depenCability will be submitted 8/82.
28 B.28 II.E.1: Additional accident The information required to monitoring resolve this issue will be instrumentation, available 12/82.
attachments 1, 2. 3. /
Status of Callaway and Wolf Creek SER Issues Issue Status / Remarks CAL WC, 28 II.G.1: Emergency power for This issue is closed, refer to pressurizer equipment.
Wolf Creek SER. Statement required in Callaway SSER.
28 A.8 II.K.1: IE bulletins on measures This issue will be confirmed to mitigate small-break after procedures are finalized LOCAs and loss of feed-in early 1983.
water accidents 28 B.28 II.K.2.13: Thermal mechanical A Westinghouse Owners Group' report--effect of report on this issue was high-pressure on submitted in 12/81. NRC has vessel integrity for the action.
small-break LOCA with no auxiliary feedwater 28 8.28 II.K.3.2: Report on overall The NRC has the action on this safety effect of issue.
PORV isolation system 28 B.28 II.K.3.ll: Justification of The NRC has the action on this issue.
use of cirtain P0RVs 28 A.8 III.A.2: Improving Licensee Callaway state and local emergency Emergency Preparedness plans are scheduled for submittal
--Long-Term 8/82. Wolf Creek submittal of revised emergency plan scheduled for 7/82.
28 8.28 III.D.l.1: Integrity of systems A submittal on this issue will outside containment be made by 2/83 for Callaway, 8/83 likely to contain for Wolf Creek.
radioactive material 29 B.24 Separation of Cables Old Lic. Condition #17.
NRC action is a site visit. 'Same as Callaway confirmatory Item #23.
30 B.4 See outstanding issue #8 NRC has the action.
N/A A.1 UHS dam dispersiveness NRC has the action.
N/A A.2 Main dam seepage KGE will make a submittal 7/82.
N/A A.3 Site-specific seismid KGE made a submittal on structures structrual analysis in 4/82. Additional information will be provided 7/82.
'I h/A-A.4 Identification of base Information will be provided by matal and heat-affected 7/82.
zone surveillance material i
N/A A.5 Pressure-temperature limits Information will be provided by.
7/82.
Status of Callaway and Wolf Creek SER Issues Issue Status / Remarks CAL WC
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III. License Conditions:
1 B.1 Surveillance of Hafnium A letter will be submitted control r ds by 6/15/82.
2 B.2 The applicant must provide No action required prior an initial inservice inspection to fuel load, program which conforms to the applicable ASME Code edition and 10 CFR Part 50 3
B.3 The applicant must implement No remarks required.
the secondary water chemistry i
monitoring and control program proposed in the SNUPPS FSAR (through revision 6) and their letter dated May 8, 1981 4
B.4 Sensor time response testing No remarks required.
5 B.5 Test of engineered safeguards An FSAR change on this issue was P-4 interlock made in Rev. 8.
A condition on the license should not be required.
NRC has the action.
6 B.6 Automatic indication of block An FSAR change on this issue of signals initiating auxiliary was made ir Rev. 8. A condition feedwater following trip of the on the license should not be main feedwater pumps required.
NRC has the action.
7 B.7 Steam generator level control An FSAR change on this issue and protection was made in Rev. 9.
A condition on the license should not be required.
8 B.8 Indicator, alarms, and test SNUPPS had committed to make features provided for instru-the changes called for by mentation and safety functions this issue. A condition on i
the license should not be required.
9 B.9 Reactor coolant temperature See confirmatory issue #10.
indicators on the auxiliary A condition on the license shutdown panel should not be required.
i 10 B.10 Actuation of valve component An FSAR change on this issue level windows on the bypassed was submitted in Rev. 8.
A and inoperable status panel condition on the license should not be required.
11 8.11 Postaccident monitoring A submittal on Reg. Guide 1.97 is planned for 6/82. 9..
,-a--
v --
Status of Callaway and Wolf Creek SER Issues Issue Status / Remarks CAL WC, 12 B.12 Interlocks for reactor coolant No' action required. A condition systems (RCS) pressure control on the license should not be during low temperature
- required, operation 13
- B.13 Volume control tank level and See confirmatory issue #11. A protection interaction condition on the license should not be required.
14 B.14 Boron dilution control See confirmatory issue #12. A condition on the license should not be required.
15 B.15 Bypass of protective trips on See confirmatory issue #16. A diesel generator condition on the license should not be required.
16 B.16 Installation of battery dis-An FSAR change on this issue was charge alarm submitted in Rev 8.
No condition on the license should be required.
17 Testing to substantiate The NRC removed this condition separation between redundant in Callaway SSER #1.
safety-related cables inside control panels 18 A.1 Compliance with Appendix R of The remaining action related to 10 CFR 50, Fire Protection Appendix R is outstanding Issue
- 10/B.3.
19 N/A Qualifications of operations No remarks required.
personnel TMI Action Plan 20 B.17 II.B.3 Postaccident sampling A submittal on this issue capability will be made by 10/82.
RLS/mtk4al4-20
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