Similar Documents at Surry |
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Category:Inspection Report
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23256A2672023-09-21021 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000280/20220042023-09-0101 September 2023 Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) IR 05000280/20230022023-08-0404 August 2023 Integrated Inspection Report 05000280/2023002 and 05000281/2023002 IR 05000280/20230012023-05-0505 May 2023 Integrated Inspection Report 05000280/2023001 and 05000281/2023001 IR 05000280/20234012023-04-21021 April 2023 Security Baseline Inspection Report 05000280 2023401 and 05000281 2023401 ML23086B9172023-03-24024 March 2023 Steam Generator Tube Inspection Report for the Fall 2022 Refueling Outage IR 05000280/20220062023-03-0101 March 2023 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2022006 and 05000281/2022006 ML23041A0232023-02-13013 February 2023 Integrated Inspection Report 05000280/2022004 and 05000281/2022004 IR 05000280/20220032022-11-0707 November 2022 Integrated Inspection Report 05000280/2022003 and 05000281/2022003, Operation of an Independent Spent Fuel Storage Installation Report 07200055/2022001, and Exercise of Enforcement Discretion IR 05000281/20224022022-10-21021 October 2022 Security Baseline Inspection Report 05000280/ 2022402 and 05000281/2022402 IR 05000280/20224042022-10-19019 October 2022 Security Baseline Inspection Report 05000280/2022404 and 05000281/2022404 IR 05000280/20224032022-09-0808 September 2022 Security Baseline Inspection Report 05000280/2022403 and 05000281/2022403 IR 05000280/20220052022-08-24024 August 2022 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Reports 05000280/2022005 and 05000281/2022005) IR 05000280/20220022022-08-0404 August 2022 Integrated Inspection Report 05000280/2022002 and 05000281/2022002 Final IR 05000280/20220112022-07-0606 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000280/2022011 and 05000281/2022011 IR 05000280/20220012022-05-11011 May 2022 Integrated Inspection Report 05000280/2022001 and 05000281/2022001 IR 05000280/20224012022-03-29029 March 2022 Security Baseline Inspection Report 05000280/2022401 and 05000281/2022401 IR 05000280/20224052022-03-22022 March 2022 Material Control and Accounting Program Inspection Report 05000280/2022405 and 05000281/2022405 IR 05000280/20220102022-03-15015 March 2022 NRC Inspection Report 05000280/2022010 and 05000281/2022010 IR 05000280/20210062022-03-0202 March 2022 Annual Assessment Letter for Surry Power Station, Units 1 and 2 (Reports No. 05000280/2021006 and 05000281/2021006) IR 05000280/20210042022-02-11011 February 2022 Integrated Inspection Report 05000280/2021004 and 05000281/2021004 IR 05000280/20210032021-11-24024 November 2021 Integrated Inspection Report 05000280/2021003 and 05000281/2021003 IR 05000280/20213012021-11-10010 November 2021 NRC Operator License Examination Report 05000280/2021301 and 05000281/2021301 IR 05000280/20210112021-11-0101 November 2021 Triennial Fire Protection Team Inspection Report 05000280/2021011 and 05000281/2021011 ML21265A4532021-10-0505 October 2021 Inspection Report 2021 FOF (IP92707) IR 05000280/20210052021-08-31031 August 2021 Mid-Cycle Letter Revised Updated Inspection Plan for Surry Power Station, Units 1 and 2 (05000280/2021005 and 05000281/2021005) IR 05000280/20210012021-08-26026 August 2021 Updated Inspection Plan for Surry Power Station, Units 1 and 2 -(05000280/2021001 and 05000281/2021001) IR 05000280/20210102021-08-16016 August 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000280/2021010 and 05000281/2021010 IR 05000280/20210022021-08-12012 August 2021 Integrated Inspection Report 05000280/2021002 and 05000281/2021002 IR 05000280/20214022021-06-14014 June 2021 Security Baseline Inspection Report 05000280/2021402, 05000281/2021402 and 07200002/2021401 ML21120A1552021-04-30030 April 2021 Integrated Inspection Report 05000280/2021001 and 05000281/2021001 IR 05000280/20200062021-03-0303 March 2021 Annual Assessment Letter for Surry Power Station, Units 1 and 2 NRC Inspection Reports 05000280/2020006 and 05000281/2020006 IR 05000280/20214012021-02-0909 February 2021 Security Baseline Inspection Report 05000280/2021401 and 05000281/2021401 IR 05000280/20200042021-02-0202 February 2021 Integrated Inspection 05000280/2020004 and 05000281/2020004; and 07200055/2020003 IR 05000281/20200402020-12-30030 December 2020 95001 Supplemental Inspection Supplemental Report 05000281/2020040 IR 05000280/20200032020-11-0606 November 2020 Integrated Inspection Report 05000280/2020003, 05000281/2020003; and 07200055/2020002 IR 05000280/20200102020-11-0505 November 2020 NRC Design Bases Assurance Inspection Report 05000280/2020010 and 05000281/2020010 IR 05000280/20200112020-09-24024 September 2020 Biennial Problem Identification and Resolution Inspection Report 05000280/2020011 and 05000281/2020011 IR 05000280/20204012020-08-25025 August 2020 Inspection Report 05000280/2020401 and 05000281/2020401 IR 05000280/20200052020-08-24024 August 2020 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2020005 and 05000281/2020005) IR 05000280/20200022020-08-10010 August 2020 Integrated Inspection Report 05000280/2020002 and 05000281/2020002 and Exercise of Enforcement Discretion IR 05000281/20200912020-07-30030 July 2020 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter; NRC Inspection Report 05000281/2020091 IR 05000281/20200902020-06-26026 June 2020 NRC Inspection Report 05000281/2020090 and Preliminary White Finding and Apparent Violation IR 05000280/20200012020-05-0808 May 2020 Integrated Inspection Report 05000280/2020001 and 05000281/2020001; and 07200055/2020001 IR 05000280/20190062020-03-0303 March 2020 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2019006 and 05000281/2019006 2024-02-06
[Table view] Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests ML23277A1172023-10-0303 October 2023 Operator Licensing Examination Approval 05000280/2023301 and 05000281/2023301 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23256A2672023-09-21021 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations IR 05000280/20220042023-09-0101 September 2023 Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 ML23244A0142023-08-30030 August 2023 Inservice Inspection Owner'S Activity Report IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) ML23226A1862023-08-10010 August 2023 Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML23220A1492023-08-0707 August 2023 Independent Spent Fuel Storage Installation - Submittal of Cask Registrations for Spent Fuel Storage ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information IR 05000280/20230022023-08-0404 August 2023 Integrated Inspection Report 05000280/2023002 and 05000281/2023002 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations ML23198A0322023-07-18018 July 2023 Regulatory Audit Report Regarding Review of License Amendment to Modify Emergency Plan Staff Augmentation Times ML23193A9382023-07-18018 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23173A0602023-07-11011 July 2023 Audit Summary for License Amendment Request Revision of the Emergency Plan to Support Relocation of the Technical Support Center ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23152A0432023-06-22022 June 2023 Audit Plan License Amendment Requests to Change Emergency Plan Staff Augmentation Times ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23151A6612023-05-31031 May 2023 ES-2.1-1, Surry 2023-301 Corporate Notification Letter (Revised) ML23167B0072023-05-31031 May 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML23130A3742023-05-10010 May 2023 Request to Delay NRC Intial Licensing Examination 2024-02-06
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML20304A2032020-10-0808 October 2020 Readiness Notification for 95001 Supplemental Inspection Notice of Violation: EA-20-057 ML20244A2832020-08-28028 August 2020 Reply to Notice of Violation; EA-20-057 ML1112300532011-05-0202 May 2011 Reply to a Notice of Violation EA-10-255, NRC Inspection Report No. 50-280/2011-012 and 50-281/2011-012, NRC Office of Investigations Report 2-2010-029 and Notice of Violation ML0623600122006-08-22022 August 2006 NRC Inspection Nos. 50/280/2006-010 & 05-281/2006-010, Reply to Notice of Violation ML0202901912002-01-18018 January 2002 Reply to a Notice of Violation NRC IR 05000280/2001-006 & 05000281/2001-006 ML19093A9191978-07-26026 July 1978 Response to a Letter of 07/12/1978, in Reference to Inspection Conducted on 05/16-19/1978, 05/22-26/1978, 06/21-23/1978 & Reported in IE Inspection Report Nos. 05000280/1978016 & 05000281/1978016 ML19093A9331978-04-11011 April 1978 Response to a Letter of 03/20/1978, in Reference to Inspection Conducted on 01/20/1978 & 01-24-25/1978 & Reported in IE Inspection Report Nos. 05000280/1978004 & 05000281/1978004 ML19093A9341978-04-11011 April 1978 Response to a Letter of 03/20/1978, in Reference to Inspection Conducted on 01/20/1978 & 01/24-25/1978 & Reported in IE Inspection Report Nos. 05000280/1978004 & 05000281/1978004 ML19093A9381978-03-22022 March 1978 Response to a Letter of 02/28/1978 in Reference to the Inspection Conducted on 01/16-20/1978 & 01/24/1978 and Reported in Inspection Reports IE-05000280/1978002 & 05000281/1978002 ML19093A9411978-03-10010 March 1978 Response to a Letter of 02/21/1978 in Reference to the Inspection Conducted on 0812/20-21/1977, 01/10-13/1978, 01/16-19/1978 & 01/25/1978 and Reported in Inspection Reports IE-05000280/1978001 & 05000281/1978001 ML19093A4041978-02-0707 February 1978 Response to Letter of 11/11/1977 in Reference to Inspection Conducted on 10/04-10/07/1977 and Reported in IE Inspection Report Nos. 05000280/1977029 & 05000281/1977029 ML19093A3911978-01-24024 January 1978 Response of Letter of 01/10/1978 in Reference to Inspection Conducted on 11/29-12/02/1977 and Reported in Inspection Report Nos. 05000280/1977035 & 05000281/1977035 ML19093A3991977-12-30030 December 1977 Response to Letter of 12/07/1977 in Reference to the Inspection Conducted on 10/25-10/28/1977 and Reported in I.E. Inspection Reports 05000280/1977031 & 05000281/1977031 ML19093A4071977-12-21021 December 1977 Response to a Letter of 11/11/1977 in Reference to Inspection Conducted on 10/04-10/07/1976 and Reported in IE Inspection Report Nos. 05000280/1977029 & 05000281/1977029 ML19093A3951977-12-14014 December 1977 Response to a Letter of 12/01/1977 in Reference to Inspection Conducted on 11/01-11/04/1977 and Reported in Inspection Report No. 05000280/1977033 & 05000281/1977033 ML19093A4081977-12-0606 December 1977 Response to a Letter of 11/11/1977 in Reference to the Inspection Conducted on 10/04-10/07/1977 and Reported in IE Inspection Reports 05000280/1977029 & 05000281/1977029 ML19093A4101977-11-30030 November 1977 Response to a Letter of 11/03/1977 in Reference to Inspection Conducted on 09/19-09/23/1977 and Reported in I.E. Inspection Reports 05000280/1977027 & 05000281/1977027 ML19093A4141977-11-0404 November 1977 Response to a Letter of 10/20/1977 in Reference to Inspection Conducted on 09/14-09/16/1977 and Reported in Inspection Reports IE 05000280/1977026 & 05000281/1977026 ML19093A4181977-10-25025 October 1977 Response to Letter of 09/27/1977 in Reference to Inspection Conducted on 08/08-08/12/1977 and Reported in IE Inspection Reports 0500280/1977022 & 05000281/1977022 ML19093A3891977-10-21021 October 1977 Response to a Letter of 09/28/1977 in Reference to Inspection Conducted on 08/30-09/02/1977 and Reported in Inspection Reports I.E. 05000280/1977024 & 05000281/1977024 ML19093A4151977-09-15015 September 1977 Response to Letter of 09/01/1977 in Reference to Inspection Conducted on 08/18-08/21/1977 and Reported in Inspection Reports IE 05000280/1977023 & 05000281/1977023 ML19093A4191977-09-0707 September 1977 Response to a Letter of 08/17/1977 in Reference to the Inspection Conducted on 08/04-08/08/1977 and Reported in Inspection Reports IE-05000280/1977021 & 05000281/1977021 ML19093A4351977-08-0101 August 1977 Reply to Letter of 07/12/4977, Concerning the Inspection of Vepco'S Surry Power Station Security Program on 05/04-05/05, 05/12-05/13, 05/23-05/26/1977 ML19093A3881977-07-15015 July 1977 Response to Letter of 06/28/1977 in Reference to Inspection Conducted on 05/24/1977 and Reported in Inspection Reports IE 05000280/1977010 & 05000281/1977010 ML19093A4511977-03-0404 March 1977 Response to a Letter of 02/25/1977 in Reference to Inspection Conducted on 01/25-01/28/1977 and Reported in Inspection Reports IE 05000280/1977002 & 05000281/1977002 2020-08-28
[Table view] |
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- . VIRGINIA _ELECTRIC AND RXCHMOND, VIRGIN-IA 2326i POWER .COMPANY.
' \
Jµly'26, 1978
, Yrro Sames P- *.--o@Reillyi,* Director_ Serial 'i:io.* 407 /071278 Office. of *.Inspection and Enfirrcement PO&H/DLB:das
_Uo S *
- Ntic lea:r_ Regt1lat.ory Cdmmisaion
. - Region Ir" .., Suite 818 .-
- *230. Peachtree Stre~:t, *rlqrthvj*est ticenae Noa i DPR.'.:.32 Atlan.t.a*~ Georgia.**_. .'30303 - * * ._ .D!?R:._37 . *.
I 1*
' Thj.s' is' in -r*esp011se t6' your' le~:tel~ of__ July 12J 1978 in *refei:.er.ce' to t';le in~
- $pect':f.on condtacted**at- Sur:1.,:.Y_ Po*wer Station on May 16-19, - 22.:.26* and juri.c/ 21-23; i978 ai;1d.rep*orte.d in-IE inspection ReportNos. 50-280/78~1'6.and 50-:-281/78*-i6. *
'He heve. :reviewed:: y~r. letter -an.<f the ~ticlo*sed .inspection_ reports. - _Our _re-
- spouse is.- contained- in .the at.tacl:nµent to *thfs* letter_. ' '. .
' ~l<lc- have d~temfued t.liat no' proprietsr.y inforrriat:!.on '1.s* 'contaiu~d in' t::h~ re-ports.,. AcGo:t'cli~ly ,' the Virgin1ai Ele~fric .. and Po~.1er; Company inter.pos<i:s. no*. ob-,_,
' jection to the~~ :iuspecd.on.' repo_rts beiµg made_ a m~t-ter of public diaclo&',Jl'e;.
. . \ ' \ . ' *,', . . . *.
'. ' .J yours
--~<2.~*Q
.
- C. M~-- Stall:;lngs * . ~ - , : _
- vice President .;. Power Supp.ly . -, ..
and Production Ope:i;ations_
- cc< Mr. Albert' Schwencer / *.
I
~
.,I (2) Continued, e *
- DESCRIPTION Administrative Procedure No. 45 - Suggestions PURPOSE Provides vehicle to suggest im-provements in procedures, methods, and safety.
Corporate Policy Statement Relates VEPCO's policy to excellence.
Policy Statement Describes open door policy and lists phone numbers to call in the event a safety situation is not rectified.
10 CFR 21 Describes reporting requirements upon discovery of any deficiency or non-compliance contrary to nuclear safety.
Notice to Employees The phone numbers in NRC to call if a problem cannot be resolved at the station.
In addition, the following actions were taken:
(a) Establishment of a program to improve access to snubbers on both units .
. (b) Post all minutes of the Station Nuclear Safety and Operating Committee meetings for two weeks.
(c) Appointed individual to provide feedback to non-supervisory employees who have submitted documents pointing out problems or suggestions.
(d) A similar program is currently being conducted at our North Anna Facility.
(3) Review of safety issues by appropriate levels of management commensurate with the importance of the issues.
Many avenues are available to employees to report safety problems. The most effective are those prescribed in Administrative Procedure 4.4, Employee Safety.
This procedure established an Employee Safety Committee made up of a representative from each department. This committee receives all reports of safety hazards from station employees and attempts to rectify them. If the committee is unable to recti-fy the proQlem, they forward them to Station Management for resolution. Station Management then takes appropriate action to resolve the problem. Reports of signi-ficant safety hazards that present a serious and imminent threat to station employees are brought to the attention of all employees and st.2.tion management immediately*.
Station Management reacts immediately to those problems and resolves them on the same day as reported.
RESPONSE TO INFRACTIONS LI~TED e IN NRC REGION II INSPECTION ~*ORT 78-16 OF JULY 12, 1978
A. Criterion XVII of Appendix B to 10 CFR 50 as implemented by the Vepco Nuclear Power Station Quality Assurance Manual, Section 11.5.3.4 and form 888.85, Periodic Test Critique, requires, in part, that inspection and test records shall as a minimum identify the results, the accepta-bility, and the action taken in connection with any deficiencies noted.
Contrary to the above, the failure of hydraulic suppressors on Unit 2 to meet the fluid level acceptance criteria during the performance of visual inspection of hydraulic shock suppressors in April 1978 and the corrective actions taken in connection with these deficiencies were not documented in the test results record or in Periodic Test Procedure No.
39, dated April 7, 1978.
This is an infraction (Unit 2).
VEPCO RESPONSE:
This infraction is correct as stated.
- 1. Corrective steps taken and results achieved.
The error in documentation of the results of the inspection is at-tributed to the fact that the wording of the inspection procedure permitted inspector to exercise broad latitude in determining operability. The fol-lowing changes have been made to the procedural aspects of the inspection:
(1) Procedure changed to delineate specific inspection criteria re-quiring the inspector to identify only a "Pass-Fail" for each inspection item for each snubber.
(2) Division of inspection procedures into "AS FOUND" for the end of the inspection interval and "AS LEFT" for the beginning of the inspection interval with unique inspection criteria for each.
(3) Provisions for independent evaluation of snubber inspection re-sults to determine and document "operability".
Inspections conducted under the new procedure have achieved the intended results of providing timely and proper evaluation of snubber deficiencies and timely notification to management of status of snubbers.
(4) The revised Periodic Test requires QC participation .
VEPCO RESPONSE:
e(Continued)
- 2. Corrective steps to be taken to avoid further non-compliance:
In that inspections conducted under the new procedures are achieving the results intended, no further corrective steps are anticipated.
- 3. Date when full compliance will be achieved:
As noted above, the revised inspection procedure is achieving the necessary results, therefore, full compliance in this area has been achieved .
RESPONSES TO INFRACTIONS IN NRC REGION II INSPECTIO 78-16 OF JULY 12, 1978
B. Technical Specification 4.17A requires that a visual inspection be performed within 31 days+ 25% (7 days) when eight or more hydraulic suppressors are identified as inoperable.
Contrary to the above, a visual inspection of Unit 2 hydraulic suppressors was not performed until approximately 48 days after 26 of the suppressors failed to meet the fluid level acceptance criteria specified in Periodic Test 39. This is an infraction (Unit 1).
VEPCO RESPONSE:
The infraction is correct as stated.
- 1. Corrective steps taken and results achieved:
This infraction is related to Infraction A stated above, in that management response in setting the inspection interval was based on the do-cumentation of the inspection. The procedure changes described in the response to Infraction A have also served to provide management with the information
- necessary to direct operations. Inspections and evaluations under the revised procedure have served to inform management of the inspection result so that current inspection intervals are considered correct and proper.
- 2. Corrective steps taken to avoid further non-compliance:
The revised procedures now in use are providing the required results.
No further corrective measures are anticipated.
- 3. Date when full compliance will be achieved:
Full compliance is now being achieved.
RESPONSES TO INFRACTION~STED IN NRC REGION II INSPECTION REPORT 78-16 OF JULY 12, 1978
C. Technical submitted Specification 6.6.2.b.(2) requires that a written report be to the Director of the appropriate NRC Regional Office with-in thirty days when conditions leading to operation in a degraded mode permitted by a limiting condition for operation are identified.
Contrary to the above, two operable hydraulic shock suppressors identi-fied on Unit 2 during the performance of Periodic Test 39 on April 7, 1978, were not reported to the NRC.
This is an infraction (Unit 2).
VEPCO RESPONSE:
The infraction is correct as stated.
- 1. Corrective steps taken and results achieved:
The inspection procedure has been revised to require that in-operable snubbers are identified for reporting as items leading to opera-
- tion in a degraded mode and therefore reportable in accordance with Techni-cal Specification 6.6.2.b.(2). The intended results have been achieved.
- 2. Corrective steps taken to avoid further non-compliance:
Actions taken in revision of the procedures have achieved the desired result. No further action is necessary.
- 3. Date when full compliance is achieved:
Full compliance has been achieved .
e RESPONSES TO INFRACTIONS ~TED IN NRC REGION II INSPECTION REPORT 78-16 OF JULY 12, 1978
D. Technical Specifications 6.1.C.l.e.4 and 6.1.C.l.e.7 specify that the Station Nuclear Safety and Operating Committee shall review all pro-posed modifications to systems which would constitute a design change and that the committee determine whether or not the proposed modifica-tions involve an unreviewed safety question.
Contrary to the above, two eight-inch containment isolation valve discs (MOV-CS-lOlA and MOV-CS-lOlB) on Unit 1 were modified in May 1978, a groove approximately 2 inches deep was cut radially in each disc, with-out prior committee review.
This is an infraction (Unit 1).
VEPCO RESPONSE:
The infraction is correct as stated.
L Corrective steps taken and results achieved:
Since the condition was identified with the unit in a cold shutdown
- condition, the full review of outage maintenance activity had not been complet-ed. Questions, other than those from the NRC inspection team, remained un-answered as to the acceptability of the valve discs and they were changed out for new discs of the unaltered configuration. The affected valves were satis-factorily leak tested with the new discs.
- 2. Corrective steps taken to avoid further non-compliance:
Station personnel responsible for repair and maintenance activities have been reinstructed on the limitations of scope of work that may be perform-ed as maintenance action.
- 3. Date when Full Compliance will be achieved:
Full compliance has been achieved.
0
. . . RESPONSES TO INFRACTIONS LI
~IN NRC REGION II INSPECTION RE 78-16 OF JULY 12, 1978
E. Technical Specification 6.4.A. and D requires that procedures for testing and corrective maintenance shall be followed.
Contrary to the above, Periodic Test 16.4, Containment Isolation Valve Leakage, and MMP-C-C-001, Corrective Maintenance for Valves in General, were not followed in that foreign substances such as beeswax and grease were utilized as valve disc lubricants on valves MOV-CS-210C and D, RS256A, RS156B, and VP-12. Addi-tionally, an evaluation was not performed to determine the effect that the foreign substance would have on the valve leakage test results.
This is an infraction (Units 1 and 2).
VEPCO RESPONSE:
The infraction is correct as stated.
- 1. Corrective steps taken and results achieved:
On May 30th, an Administrative memorandum was issued which pro-hibited the use of foreign materials in valves whose leak tightness is demonstrated in the performance of PT-16.4. In addition, on June 1st a change to MMP-C-G-001 was approved which required as the last step prior to close out, "an inspection for internal acceptability, i.e. intervals of integrity, cleanliness, foreign material, etc."
Q.C. witness of the close out was also added in the procedure change.
Further action taken to insure the current unit operation is not hazarded by any effect was to conduct an in depth evaluation of all valves tested under 10 CFR 50, Appendix J to determine that the valves meet contaiIJIDent leakage acceptance criteria with the assistance of any foreign substance. Valves which could not be determined with a high degree of confidence to be free of foreign material were opened, in-spected and re-closed using the procedure change as described above.
In addition, leakage tests of selected valves were made to determine the affect of lubricating substances. Further evaluation of lubricants is anticipated.
- 2. Corrective steps to be taken to avoid*further non-compliance:
Procedure changes will be initiated to incorporate additional information as it is =eceived re 6 ~=~ing the use of approved lubricants for valve seat and disc protection.
- 3. Date when full compliance will be achieved.
- Full compliance has been achieved .
e RESPONSES TO INFRACTIONS L IN NRC REGION II INSPECTION R 78-16 OF JULY 12, 1978
F. Criterion XVI (corrective action) of 10 CFR 50 Appendix B requires, in part, that the identification of the significant condition adverse to quality, the cause of the condition, and the corrective action taken shall be documented. Section 17.2.16 of VEP-1-A, Quality Assurance Program Topical Report, requires that corrective maintenance of nuclear safety related material be documented on a maintenance report. Section 16 of the Nuclear Power Station Quality Assurance Manual (NPSQAM) re-quires in paragraph 6.5.4.d that maintenance procedures include provi-sions for the signature of the individual completing the work.
Contrary to the above, the provisions of the NPSQAM were not followed in that certain safety related maintenance actions on Units 1 and 2 were completed by individuals other than those executing the documenta-tion in the maintenance procedure or maintenance report. Examples in-clude maintenance reports issued in April 1978 that involved maintenance of the Emergency Diesel Generator No. 1, Repair of Fuel Cooling Pump FC-P-3B; and performance of Periodic Test Procedure No. 39 on Unit 2 snubbers.
This item is an infraction (Units 1 and 2) .
The infraction is correct as stated.
- 1. Corrective steps taken and results achieved.
Maintenance personnel have been re-instructed to emphasize the proper handling of procedures. Emphasis was placed on proper me-thods of completing procedures, (i.e. the craftsmen must sign the steps he performs). Also, emphasis was placed on proper documentation and routing for steps requiring procedure deviations.
- 2. Corrective steps taken to avoid further non-compliance:
No further action is necessary.
- 3. Date when full compliance is achieved.
Full compliance has been achieved .