Letter Sequence Other |
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Results
Other: 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant, 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420, A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage, BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001, GO2-88-084, Submits Info as Requested by NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, GO2-88-153, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Results of Reinsp of Nine Breakers After Removal of Spring Provided, ML17251B046, ML17284A611, ML18152A818, ML20147F998, ML20147G854, ML20148A890, ML20148B666, ML20148K225, ML20148Q724, ML20149M198, ML20150A899, ML20150B182, ML20150B526, ML20150C407, ML20150C743, ML20150D397, ML20151A945, ML20151B202, ML20151E018, ML20151E419, ML20151E868, ML20151G115, ML20151G791, ML20151H779, ML20151H965, ML20151Q920, ML20154D233, ML20154E154, ML20155A456, ML20155E392, ML20196H353, ML20205P688, ML20235J165, ML20235J168, ML20236A614, ML20236A849, ML20236D105, ML20236F547, ML20236S018, ML20247K075, NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers, RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant, W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin
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MONTHYEARML20235S2971987-10-0202 October 1987 Summary of 870923 Meeting W/Westinghouse Re Technical Basis for Westinghouse Recommended Actions,Criteria & Conclusions in to Utils That Use Models DS-416,DSL-416, DS-420,DS-206 & DSL-206 Switchgear in Class 1E Svc Project stage: Meeting ML20236A6141987-10-16016 October 1987 Advises That Util Insp of Reactor Trip Breakers Revealed Catawba Pole Shaft Which Had Welds W/Indications of Cracking.Forwards Informal Technical Communication from Franklin Research Ctr Re Initial Observation Project stage: Other ML20236A8491987-10-16016 October 1987 Forwards I.6177-5-1, Interim Rept on McGuire Reactor Trip Breaker 2B Failure Evaluation & Rcommended Corrective Actions from Westingtonhouse. Rept Explains Mechanical Binding Which Kept Breaker from Opening on 870702 Project stage: Other ML20236D1051987-10-21021 October 1987 Provides Record of 871020 Telcon Between D Hood,D Sellers & V Hodge of NRC & J Mcvicker & Cowne of Bg&E Re Unit 1 480 Volt Circuit Breaker W/Broken Weldment Connecting Ctr Pole Lever to Pole Shaft.Util Exam Results in 860918 Memo Project stage: Other ML20236F5471987-10-23023 October 1987 Documents 871020 Telcon W/Util Re Unit 2 Circuit Breaker Pole Shaft Weld Failure Project stage: Other ML20236F9651987-10-27027 October 1987 Notification of 871103 Meeting W/Util & Westinghouse in Philadelphia,Pa to Discuss Results of Franklin Research Ctr Exam of Cracks in Pole Shaft Welds of Reactor Trip Breaker Project stage: Meeting ML20236S0181987-11-18018 November 1987 Summarizes 871020 Telcon Between NRC & Util Re Two Broken Fillet Welds on Pole Shaft Assembly of Circuit Breaker That Energizes Emergency Fire Protection Pumps for Facility. Photographs Attached to 870710 Memo to NRC Encl Project stage: Other ML20149M1981988-02-16016 February 1988 Advises That Since Util No Longer Operating Reactor Licensee Due to 870430 Shutdown & 870804 Amend,Modifying License DPR-45 to Possess But Not Operate Status,Generic Ltr 88-01 Determined Inapplicable to Facility Project stage: Other 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-4201988-02-23023 February 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420 Project stage: Other ML20196H3531988-02-25025 February 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility Project stage: Other ML20147G8541988-03-0101 March 1988 Responds to NRC Bulletin 88-001 Re Westinghouse Ds Series Circuit Breakers Used in safety-related Applications.Plant Does Not Have Any Westinghouse Ds Series Circuit Breakers Project stage: Other ML20147F9981988-03-0404 March 1988 Submits Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Author Does Not Utilize Any Westinghouse Circuit Breakers,As Identified in Subj Bulletin,In Class 1E Applications at Facility Project stage: Other ML20150B1821988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breakers in Class 1E Applications So Bulletin 88-001 Does Not Apply to Plant Project stage: Other ML20148A8901988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Unit 1 Has No Westinghouse Ds Circuit Breakers Used in Class 1E Application.Unit 2 Reactor Trip & Bypass Breakers Insp Initiated Per Info Notice 87-035 Project stage: Other ML20150A8991988-03-0909 March 1988 Provides Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Series Ds Circuit Breakers Not Employed at Plant.Insp Required by Bulletin Not Applicable to Plant Project stage: Other ML20150C4071988-03-11011 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Type Ds Circuit Breakers Not Used at Plant Project stage: Other BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-0011988-03-15015 March 1988 Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001 Project stage: Other ML20148B6661988-03-16016 March 1988 Responds to 880205 NRC Compliance Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Westinghouse Ds Series Circuit Breakers Not Used in Class IE Svc at Plant Project stage: Other NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers1988-03-24024 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers Project stage: Other ML20148K2251988-03-25025 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Two Reactor Trip Breakers & Two Reactor Trip Bypass Breakers Subj to Bulletin Used at Millstone Unit 3.Main Pole Shaft Weld Insps Completed by 880225 Project stage: Other ML20151G7911988-03-28028 March 1988 Confirms That Westinghouse Ds Breakers Not Used at Facility, Per IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers Project stage: Other W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin1988-03-29029 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin Project stage: Other ML20151A9451988-03-30030 March 1988 Responds to IE Bulletin 88-001 Re Westinghouse Ds/Dsl Circuit Breakers.Ref Components Not Utilized at Facility Project stage: Other 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant1988-04-0101 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant Project stage: Other ML20151B2021988-04-0404 April 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Insp of All Westinghouse DS-415 Reactor Trip & Bypass Breakers Completed on 880308 & Results Encl Project stage: Other RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant1988-04-0404 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant Project stage: Other ML18152A8181988-04-0505 April 1988 Responds to IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Type Ds Breakers Used at Plant Project stage: Other ML20148Q7241988-04-0707 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch Project stage: Other ML17251B0461988-04-0707 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Plant Does Not Have Westinghouse Circuit Breakers Subj to Bulletin Project stage: Other ML20151H7791988-04-0707 April 1988 Informs That Westinghouse Ds Circuit Breakers Not Utilized in Any 1E Application at Plant But Used in non-1E Applications & Will Be Included in Util Preventive Maint Program Project stage: Other ML20151E4191988-04-0808 April 1988 Responds to 880205 NRC Bulletin 88-01 Re Defects in Westinghouse Circuit Breakers for Facilities.Westinghouse Ds Series Circuit Breakers Not Used at Plants.Other Provisions of Bulletin Do Not Apply to Plants Project stage: Other ML20151E8681988-04-11011 April 1988 Forwards Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers in Class 1E Svc.All Required long-term & short-term Insps Completed Project stage: Other GO2-88-084, Submits Info as Requested by NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers1988-04-11011 April 1988 Submits Info as Requested by NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Project stage: Other ML20151G1151988-04-13013 April 1988 Ack Receipt of in Response to NRC Bulletin 88-001 Re Westinghouse Circuit Breakers.Plant Does Not Use or Plan Use of Circuit Breakers,Therefore Matter Closed Project stage: Other ML20151H9651988-04-13013 April 1988 Responds to NRC Bulletin 88-001, Deficiencies in Westinghouse Circuit Breakers. Bulletin Addresses Deficiencies Exclusive to Westinghouse Ds/Dsl Type Circuit Breakers & Outlines Specific Insps to Be Performed Project stage: Other ML20205P6881988-04-20020 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Circuit Breakers Subj to Bulletin Installed in Plant Project stage: Other ML20153E9001988-05-0404 May 1988 Ack Receipt of Responding to NRC Bulletin 88-001, Defects in Westinghouse Circuit Beakers. Response to Bulletin Complete & Matter Closed Project stage: Other ML20155E3921988-06-0909 June 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit breakers.Sixty-six of sixty-seven Breakers Required New Pole Shafts Due to Failure of Welds to Meet Bulletin Requirements Resulting from Insp Project stage: Other ML20150C7431988-06-28028 June 1988 Forwards Arvin/Calspan Investigation of Trip Breaker Failure..., Explaining Mechanical Binding Which Caused Failure on 870702 Project stage: Other ML20150B5261988-06-30030 June 1988 Informs That All Class 1E DS-416 Breakers Now in Use Comply W/Nrc Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers Project stage: Other ML20150D3971988-07-0505 July 1988 Advises That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other GO2-88-153, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Results of Reinsp of Nine Breakers After Removal of Spring Provided1988-07-13013 July 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Results of Reinsp of Nine Breakers After Removal of Spring Provided Project stage: Other ML20151E0181988-07-14014 July 1988 Advises That Util 880407 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151Q9201988-08-0202 August 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20154E1541988-09-0909 September 1988 Advises That 880408 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20154D2331988-09-0909 September 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory & No Further Reply Necessary Project stage: Other ML20155A4561988-09-29029 September 1988 Requests Addl Info Re Util 880908 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Response Requested within 70 Days of Ltr Date Project stage: Other ML17284A6111988-11-18018 November 1988 Advises That Util 880411 & 0713 Responses to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory Project stage: Other ML20235J1651989-02-17017 February 1989 Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers Project stage: Other ML20235J1681989-02-17017 February 1989 Advises That 880314 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications at Plant Project stage: Other 1988-03-07
[Table View] |
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch| ML20148Q724 |
| Person / Time |
|---|
| Site: |
Hatch, Vogtle, 05000000 |
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| Issue date: |
04/07/1988 |
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| From: |
Gucwa L GEORGIA POWER CO. |
|---|
| To: |
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
|---|
| References |
|---|
| IEB-88-001, IEB-88-1, SL-4446, TAC-65955, TAC-65956, TAC-67675, TAC-67676, NUDOCS 8804130275 |
| Download: ML20148Q724 (5) |
|
Text
-. __. _ _ _ _
e
, 9. 33 P ont A
,3 At!anta, Georg a 30308 Trephone 404 526-6526 Maling Adtess.
Post Oace Box 4545 At'anta. Georg a 30302 Georgia Power L.T.Gucwe F* 8M" N'C 3YSI""
Manage Nuciear Safety SL-4446 and Lcensno 0887U X7GJ17-C110 April 7, 1988 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Hashington, D. C.
20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 PLANT V0GTLE - UNITS 1, 2 NRC DOCKETS 50-424, 50-425 OPERATING LICENSE NPF-68 CONSTRUCTION PERHIT CPPR-109 TACS 65955/65956 RESPONSE TO NRC BULLETIN 88-01 "DEFECTS IN HESTINGHOUSE CIRCUIT BREAKERS" Gentlemen:
The subject NRC Bulletin, dated February 5,
1988, requested that Georgia Powar Company submit a letter of confirmation for completion of inspections for certain Westinghouse circuit breakers.
The Georgia Power Company response is provided in the enclosure to this letter.
If you have any questions in this regard, please contact this office.
Mr.
L. T. Gucwa states that he is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
Sincerely,
%~ h L. T. Gucwa Sworn to and subscribed before me this 7th day of April, 1988.
?
Wy-~~ " k $cnh l
Notar9Public
% % cassion osuus.h HJB/ju k ta,im
Enclosure:
Response to NRC Bulletin 88-01 c:
(see next page) l$0* $00h !
$1 i
G
GeorgiaPower A U. S. Nuclear Regulatory Commission April 7,1988 Page Two c: Georala Power Comoany Mr. J. T. Beckham, Jr., Vice President - Plant Hatch i
Mr. P. D. Rice, Vice President and Vogtle Project Director Mr. G. Bockhold, Jr., General Manager - Plant Vogtle GO-NORMS U. S. Nuclear Reaulatory Commission. Washinaton. D. C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch Mr. J. B. Hopkins, Licensing Project Manager - Vogtle (2 copies)
U. S. Nuclear Reaulatorv Commission. Realon II Dr. J. N. Grace,' Regional Administrator ~
Mr. P. Holmes-Ray, Senior Resident Inspector - Hatch Mr. J. F. Rogge, Senior Resident Inspector, Operations - Vcgtle Mr. R. J. Schepen, Senior Resident Inspector, Construction - Vogtle 9
l f
1 I
I i
0887U i
P00775
GeorgiaPowerA ENCLOSURE PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 PLANT V0GTLE - UNITS 1, 2 NRC 00CKETS 50-424, 50-425 OPERATING LICENSE NPF-68 CONSTRUCTION PERMIT CPPR-109 TACS 65955/65956 RESPONSE TO NRC BULLETIN 88-01 "DEFECTS IN HESTINGHOUSE CIRCUIT BREAKERS" In this enclosure, Georgia Power Company (GPC) presents its response to NRC Bulletin 88-01, "Defects in Hestinghouse Circuit Breakers", for Plants Hatch and Vogtle.
The Bulletin requires a determination of the number and Class 1E use of five specific breaker models (Hestinghouse CS-206 DSL-206,05-416, DSL-416, and DS-420).
If the breakers are found, the Bulletin requires short and long term inspection snd reporting of the inspection results.
If none of the referenced breake.s are found, then the Bulletin requires an affidavit to that fact.
It is our understanding that subject replacement breakers or parts from Hestinghouse require a certificate of compliance with this Bulletin.
PLANT HATCH There are no Hestinghouse model DS-206, DSL-206, DS-416, DSL-416, or DS-420 breakers in Class 1E circuits at Plant Hatch.
This completes the requirements for the subject Bulletin for Plant Hatch.
PLANT V0GTLE UNIT 1 There are eight of the subject breakers in the following uses at Plant Vogtle Unit 1:
two Reactor Trip Breakers (RTBs), two Reactor Trip Bypass Breakers, two Motor-Generator Ground Control Circuits (non-lE application), and two spares.
All of these breakers are model DS-416.
The subsequent discussion for this unit will refer only to the six Class IE breakers.
These breakers were examined under the criteria of the Hestinghouse September 11, 1987 Service Advisory Letter (SAL) on October 16, 1987, during a maintenance outage.
The SAL criteria had been incorporated into Maintenance Procedure 27765-C, Pev 9
"Hestinghouse Type DS 416 Circuit Breaker Maintenance".
The inspection results are maintained for the installed Class lE breakers only.
At the time of the SAL inspections, there was no observed mechanical misalignment.
However, one of the main pole shaf ts (RTB "B") failed the inspection and was removed from service.
Although RTB "B"
passed the acceptance criteria of the SAL, it was rejected by GPC based on a lack of fusion across the weld fillet near the center of its length.
'It is believed that this pole shaft would not have passed the criteria of the Bulletin.
Upon rejection, the entire breaker was replaced with an inspected Class IE spare and Hestinghouse was contacted to obtain a replacement shaft.
The replacement was received in January 1988.
0887U E-1 04/07/83 SL-4446 P00775
GeorgiaPower d ENCLOSURE (continued) l
~
"DEFECTS IN HESTINGHOUSE CIRCUIT BREAKERS" The SAL was incorporated verbatim into Westinghouse Technical Bulletin NSID-TB-87-11.
The Westinghouse Technical Bulletin was in turn embodied into the NRC Bulletin 88-01'.
While evaluating the SAL inspections against the requirements of the NRC Bulletin, it became apparent that the additional weld inspection criterion for porosity imposed by Bulletin 88-01 mandated reinspection of the main pole shafts.
Although porosity / surface indications are an inherent part of visual weld inspections, the specifk criterion was not reflected in Procedure 27765-C, Rev.
9, and
- was, therefore, not previously documented.
Procedure 27765-C has been revised to include the NRC Bulletin's visual weld inspection acceptance criterion.
The short and long term inspections in accordance with Bulletin 88-01 were combined and conducted March 5 through March 10, 1988, for Class 1E breakers while the unit was at 100% power.
One pole shaft (Bypass "B")
failed the inspection for excessive porosity in terms of the NRC Bulletin's requirements.
The breaker was removed from service.
There were no mechanical misalignments.
The failure of the pole shaft on Bypass "B"
was not detected on the previous inspection because of the lack of a specific porosity criterion.
A replacement is on order from Westinghouse.
When it is received, the breaker will be inspected and retained as a spare.
These actions complete the requirements of the subject Bulletin for Plant Vogtle Unit 1.
PLANT V0GTLE UNIT 2 There are six of the subject breakers in the following uses at Plant Vogtle Unit 2:
two RTBs, two Reactor Trip Bypass Breakers, and two Motor-Generator Ground Control Circuits (non-1E application).
All of these breakers are model DS-416.
The subject inspections will be completed for the four Class 1E applications prior to fuel load (expected in early 1989).
The inspection results are expected to be forwarded to the NRC within 30 days of completion.
ADDITIONAL INFORMATION The NRC requested additional information to evaluate the cost of complying with Bulletin 88-01 in the following areas:
(1) "staff time to perform requested inspections, corrective actions, and associated operability testing:"
During an inspection performed in October 1987, Plant Vogtle personnel expended approximately 148 manhours among Maintenance, Engineering, Quality Control, and Operations.
This does not include the time of the NRC or Westinghouse personnel who also witnessed the inspections.
0887U E-2 04/07/88 SL-4446 700776
GeorgiaPower d ENCLOSURE (continued)
"DEFECTS IN HESTINGHOUSE CIRCUIT BREAKERS" During the inspection in March 1988, Plant Vogtle personnel expended approximately 171 manhours among Maintenance, Engineering, Quality Control Operations, and Nuclear Safety and Compliance.
This does not include the time to replace the pole shaft.
No significant costs were incurred for Plant Hatch.
(2) "staff time to prepare requested documentation":
A total of 80 manhours has been expended in preparing the requested documentation.
This time is divided among Plants Vogtle and Hatch Nuclear Safety and Compliance groups and the corporate office Engineering and Nuclear Safety and Licensing groups.
(3) "additional cost incurred as a result of the inspection findings (e.g.,
costs of corrective actions, costs of downtime)":
There is no easy determination of inspection cost for the October inspections.
For the March inspections, there was no "downtime" cost as the inspections were performed at power.
The replacement pole shafts are being provided to GPC at no charge by Westinghouse.
No significant costs were incurred for Plant Hatch.
i I
6 0887U E-3 04/07/88 SL-4446 rwm
-..-