ML20246J119
| ML20246J119 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/20/1989 |
| From: | Dunlap B, Riley R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20246J098 | List: |
| References | |
| PE-0012, PE-0012-R00, PE-12, PE-12-R, NUDOCS 8909050041 | |
| Download: ML20246J119 (61) | |
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X TECHNICAL REPORT NO. PE-0012 REY. O RESPONSE TO SSOMI ITEM IC-8 0F NRC JUNE 26, 1989 LETTER NORTH ANNA PROJECT ENGINEERING POWER ENGINEERING SERVICES VIRGINIA POWER JULY 19, 1989 PREPARED BY: M>wdQ T /9/98f REVIEWED BY: fBote,= K/ L Lev 5 Anwu pe<Tel co. d nol.u nn sq(9 tz, R. k d e g o n 1 419 ti /
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APPROVED BY:
al. MI __ dutu, 't.o,. /924 QUALITY ASSURANCE CATECJRY SAFETY RELATED 8909050041 890825 "
PDR O ADOCK C5000339 -
PNU 135-BSD-71409-1
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t b , ' TABLE OF CONTENTS 'I h . .
- RESPONSE TO S$0MI ITEM IC-8 0F NRC JUNE 26, 1989 LETTER" l
COVER-PAGE 1 TABLE 0F CONTENTS 2
1.0 INTRODUCTION
. 3 12.0L METHODOLOGY- 3 j 3.0 VERIFICATION 4 q L -
3.1 Item IC-8.(1) 4 l 3.2'. Item IC-8 (2) 8 3.3 Item IC-8 (3) 11
4.0 CONCLUSION
S 15 )
4.1 Review of Response' 15 4.2 Review of Impact 16 j i
5.0 ' REFERENCES. 17 6.0' ATTACHMENTS Attachment 1 Unit 2 Outage - DCPs & EWRs - DCPs Reviered for Additional Functional Testing .l Attachment 2 Unit 1 Outage. - DCPs & EWRs - (DCPs Reviewed for !
Additional Functional Testing)
Attachment 3 Unit 2 EWRs Reviewed Attachment 4 EWRs Reviewed May 1 through July 5, 1989.
Attachment 5 EWRs Reviewed Between July 5 and July 12, 1989.
Attachment 6 Memorandum from G. A. Rosetti to B. S. Dunlap dated July 14, 1989.
Attachment 7 Memorandum from S. L. Harvey to D. A. Heacock dated March 29, 1989.
Attachment 8 Memorandum from S. L. Harvey to D. A. Heacock dated May 4, 1989. ;
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- 1.0; INTRODUCTION J LThe' Nuclear Regulatory Commission Office of Nuclearr.eactor Regulation conducted a Safety-System Outage Modification Inspection-(SSOMI) of North Anna' Power Station design support.during February 13 .17 and February 27 g - March 3. 1989. During.the course of the SS0MI, NRC NRR posed many questions, some of which could not be answered to their satisfaction when discussed. These questions were recorded, assigned a serial number, and responded to in writing. .One such question was question NE-001 for which' three written responses were provided.
This question was considered resolved by Virginia Power based on the responses provided and the information provided during the exit meeting.
The NRC in their letter of June 26, 1989 which provided their review of the results of the SS0MI, included items based on this initial question and the related, " safety significant matter" item 4 from their letter of March 17, 1989 as Finding IC-8. The finding IC-8 is worded somewhat differently and includes requests which were not stated in earlier correspondence.
2.0 METHODOLOGY The NRC finding Item IC-8 requests that VEPC0 confirm three conditions have been met in order to resolve this open item. The three conditions are:
"(1) The post-modification testing requirements had been included in all the design change packages / engineering work requests installed during this outage and the required testing was implemented subsequent to modification installation.
(2) The design change process and engineering work request procedure have been updated to require' inclusion of post-modification testing requirements from project engineering and implementation by the site test group.
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13 (3) ' The two aforementioned safety' injection tests were' completed L subsequent to the ATWS modification'."-
> This report in Section 3.0 Verification will: review each item and review p : related' previous information, prior correspondence procedures and documentation to establish the Virginia Power current status relative to each condition'of-Item IC-8.
3.0- VERIFICATION This sectior, will provide the NRC current and any previous position for each of the three conditions of Item 10-8, fo? lowed by the Virginia Power previous and current position and verification of the information included:
3.1 -NRC I' tem IC-8, (1) 3.1.1'-NRC position per'their' June 26, 1989 letter.
"The post-modification testing requirements had been included-
'in all the design change packages / engineering work requests installed during this outage and the. required testing was implemented subsequent to modification installation."
3.1.2 NRC position per their March 17, 1989 letter.'
"To ensure that the modifications being installed during the current outage are functionally tested subsequent to installation and to ensure that the capability of the affected systems to mitigate the design basis accidents has not been compromised. VEPCO was requested to incorporate the specific post-modification testing requirements into the design change packages or engineering work requests scheduled to be installed for this outage."
3.1.3 Previous Virginia Power Response 135-BSD-71409-4
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-3.1.3.1 March 31, 1989 letter 89-206 Item 4.
" Design' Change Packages (DCPs) and Engineering, Work )
Request (EWRs) being implemented during the 1989 refueling outages that affect system performance, j L are b'eing reviewed to it.nre that the following functional criteria have been met:
a.- The operational logic of the circuit is as intended by the design change for the installed
-l modification.
.b. The operational logic of any other system input tooroutputfromthecircuit(s)modifiedor: )
installed is not altered by the design change except as noted in Item c, below.
- c. The modified circuit output operational logic remains unchanged unless it is'specifically ;
altered by the. design change."' 3 3.1.3.2 April 28,.1989 Letter No. 89-2068 Item 4 i "As discussed with members of your staff during a SSOMI follow-up inspection conducted the week of April 3.through 7,1989, and as stated in our letter I Serial No.89-206 dated March 31, 1989, Design Change Packages (DCPs) and Engineering Work Request (EWRs) being implemented during the 1989 refueling i
outages that affect system performance are being
! reviewed to insure that the testing criteria as
{ stated in the letter have been met. Also, j,
procedures governing DCP and EWR preparation have been revised to assure adequate functional testing ;
for the modification and affected systems is j addressed. i 135-BSD-71409-5
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t Currently, Unit 2 DCP's, to be installed during this outage, have been reviewed and appropriate changes made where necessary. The review of any EWR's implemented during this outage will be completed L prior to entering Mode 4. Unit i reviews are in progress, and will be completed prior to entering Mode 4. Backlogged EWR's and DCP's that are approved and awaiting implementation, but not yet scheduled will be reviewed prior to their implementation and being declared operable."
3.1.3.3 June 30, 1989 Letter 89-206D, Item 4.
"As discussed with members of your staff during a SSOMI follow-up inspection conducted the week of '
April 3 through 7,1989, and as stated in our letter Serial No.89-206 dated March 31, 1989, Design Change Packages (DCPs) and Engineering Work' Requests (EWRs) being implemented during the 1989 refueling outages that affect system performance are being reviewed to insure that the testing criteria as stated in the letter have been met. Also, procedures governing DCP and EWR preparation have been revised to assure adequate functional testing for the modification and affected systems is addressed.
Unit 2 DCP's and EWR's have been reviewed and appropriate changes made where necessary. The review of any EWR's implemented during the Unit 1 outage will ' oe completed prior to entering Mode 4.
Backlogged EWR's and DCP's that are approved and awaiting implementation, but not yet scheduled have been reviewed and changes made as required.
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3.1.4. Virginia Power Present Status All;DCPs and EWRs implemented during the outage were' reviewed to . verify that adequate post-modification testing was -
included and. documented. Additional-testing, testing documentation, and/or testing requirements were incorporated into DCPs and EWRs based on~these reviews.
Testing of modification is not performed until work has'been completed to a specific step or steps in a procedure.
3.1.5 Virginia Power Status Verification North Anna Advisory Operations has reviewed the EWRs and DCPs-listed in Attachments 1 through 5 of this report. The North Anna Design Control Engineer for Design Change Packages has verified that for most DCPs included ~ on Attachment 2 that a Section 3.16 regarding functional testing has been included in the DCP. A similar result would be expected for Unit 2 DCPs included in Attachment 1.
The standard for preparation of EWRs, Station Administrative Procedure 3.7, was revised on March 31, 1988 to require testing and on May 26, 1988 to require functional testing for all EWR modifications.
Station Administrative Procedure 11.1, " Design Change Test Procedures" 6.3, requires that work on EWR's and DCPs state testing be released only "Upon completion of work to the point testing can be conducted". Therefore, for EWRs and DCPs performed by Nuclear Site Services testing would occur only when work was completed to a satisfactory extent to all testing.
I For EWRs performed by cthers under the work order program require post completion testing per Step 4.18 and 4.19 of 135-BSD-71409-7 L
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Station Administrative Procedure 16.7 " Work Order
. Processing", dated . 11-01-88.
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Therefore, testing should not have been performed before work was completed to the point where the modification was ready to' test.
The' requirements of Admin. 14.0, " Tagging of Systems and/or Components", provides additional control of the performance.
of testing and aids in assuring work is completed prior to testing..
However, a detailed independent verification of the completion of work on each component or system prior to the testing of that component or system has not been performed for'each EWR and DCP worked this outage in support of this-report. However, Quality Assurance group reviews work performed'and any problems which they determine based on completions, etc., would be documented and resolved.
.3.2 NRC Item IC-8 (2) 3.2.1 NRC Position per June 26, 1989 letter.
"The design change process and engineering work request procedure have been updated to require inclusion of
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post-modification testing requirements from project engineering and implementation by the site test group."
3.2.2 Previous NRC Position per March 17, 1989 letter.
"The inspection team noted that design change packages (DCPs) did not explicitly prescribe the necessary testing required to demonstrate functionally of the system and affected components following the change. VEPC0 comitted to updating the associated procedures to ensure that the required testing would be accomplished for future modificatic15."
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3.2.3 Previous' Virginia: Power Response
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3.2.3.1 March 31, 1989 letter 89-206 Item 4
" Procedures' governing DCP and-EWR preparation will-be revised to assure that adequate functional testing f'or the modification and affected systems is both performed and documented."
L 3.2.3.2 April 28, 1989. letter 89-206B and June 30, 1989 letter 89-206D Item 4-
"Also,' procedures governing DCP and EWR preparation .
have been revised to assure adequate functional testing for the modification and affected systems is addressed."
3.2.4' Virginia Power Present Status The Design Change Package (DCP) preparation standard'and the Station Administrative Procedure for Engineering Work Requests (EWRs) have been modified to. require the inclusion of requirements and acceptance criteria for post modification testing.
Station Administrative Procedure 3.7 for EWRs requires that testing be included for all EWR modifications. Since not all EWRs result in modifications, the testing requirements are not imposed for all EWRs. Since EWRs may be prepared on site by Power Engineering Services without the involvement of a Project Engineer, the EWR standard requires the " Functional testing requirements and acceptance criteria for all testing will be determined by the preparing engineer".
The DCP preparation standard, STD-GN-0001, Rev. 8 requires that the DCP be prepared by others and reviewed and signed by 135-BSD-71409-9
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the Project Engineer or his designee and that field changes.
to a DCP be reviewed and signed'by.the Project Engineer or r : the Lead Site Engineer.
Therefore, the requirements for post-modification testing will be determined by an appropriate engineer for both DCPs and EWRs. These. requirements for DCPs will be reviewed by the Project Engineer, his designee, or.the Lead Site Engineer.
The implementation of testing will be in accordance with the Station Administrative Procedures. The testing of DCPs is implemented or coordinated by Advisory Operations with the assistance of other site groups. The implementation of
-testing of EWRs is per the appropriate Station Admins.
It should be noted that due to SSOMI concerns, Advisory Operations is reviewing all DCPs and EWRs for adequacy of testing.
3.2.5 Verification of Section 3.2.4 Paragraph one:
Requirements for post-modification testing are set forth in STD-GN-0001 Revision 8, Change Nctice Number 12 for DCPs and in North Anna Station Administrative Procedure 3.7 Step 6.12 dated February 28, 1989, and in permanent procedure deviation j i
89-002 dated and approved April 18, 1989, Paragraph two:
Testing requirements are outlined in Step 6.12 of Admin 3.7 and the related procedure deviation 89-002.
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- Paragraph.three
Requirements for these reviews and sign-offs are' included on pages'96 and 106.of Revision 8 of STD-GN-0001..
Paragraph four:
e Basis for this is Admin.- 3.7 Step _6.12b and related deviation 89-002 for EWRs and STD-GN-0001 Revision 8 pages 96 and 106' t and change notice number 12.
I Paragraph five:
The implementation of testing of DCPs is controlled by Station ~ Administrative Procedures 3.1, " Administrative Pro,cedure for Control of Design Change Implementation", dated
_May.12,'1989, and Procedure 11.1, " Design Change Test Procedures" dated December 15, 1988. The testing of EWR's is also controlled per Admin. 11.1- . Additionally, based on the workinvolved,Admins11.2,"PeriodicTest(PT) Program",
and/or Admin. 11.4, "Special Tests", may be involved.
Paragraph 6:
Mr. S. L. Harvey on July 12, 1989 informed Mr. B. S. Dunlap that this review was being performed and that a log of EWRs reviewed was being maintained. The log or log summary from the Unit 2 outage through July 5, 1989 is enclosed as Attachments 1 through 5.
3.3 NRC Item IC-8 (3) 3.3.1 NRC Position, June 26, 1989 letter.
"The two aforementioned safety injection tests were completed subsequent to the ATWS modification."
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,i *g g The~two aforementioned safety' injection tests-are stated as:
" Additionally, the team identified two examples where the post-modification testing'was' performed prior to the installation of thelATWS modification. Test' Procedure-2-PT-57-4, " Safety Injection Functional Test" included.
. auxiliary feedwater pump ~ actuation on a safety injection-
- ' signal and steam generator blowdown valves closing on a safety injection signal. Both of these tests were done prior-to the ATWS modification installation. Therefore. this. item remains open pending confirmation'from VEPC0 that
- The two aforementioned safety injection tests were completed-subsequent to the ATWS modification."
3.3.2 NRC Position in Previous Correspondence This item was not stated in previous correspondence.-
3.3.3 Virginia Power Review 2-PT-57.4 Safety Injection Functional Test is a Periodic Test (PT).and is not a post-modification test. Periodic tests may be used to perform all, part or none of the functional testing of a modification. This is based upon the i.est procedure and functional requirements of the testing, the schedule for periodic test performance and for post-modification testing, and the applicability of the PT to the post-modification testing involved.
l Virginia Power employees received initial NRC questions
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regarding the post modification testing of circuits affected I
by the installation of AMSAC on February 15, 1989. A r- response was provided as S50MI NRC question and answer form NE-001.
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I< Based on this' initial response'and discussions, the' question was reissued as NE-001;Rev.-A on February 16, 1989. .A' response was-provided on February 27, 1989.
The condssion presented at the end of. the February 27, 1989 was as-follows:
" Conclusion Therefore, though.the.DCP did not enumerate the mV 5ods used to:
verify operation and to preclude return to power with equipment not properly returned to service, the information presented herein describes, at least in part, the manner in which-operability is being verified..
Due to the need for a revision of the Engineering Review and Safety Analysis of this DCP, based on comments-from.the Station Nuclear Safety'and Operating Committee on DCP 87-11-1 in 1_ ate December, a field change is being developed for this DCP (87-12-2) and for 87-11-1. These field changes. one per DCP, will include a new section 3.16 which will further clarify the functional testing required for these DCPs."
The subject of testing was a very active one and therefore, on March 1, NRC personnel visited the site to discuss the subject with site personnel. On March 2 via NE-001 Rev. B, NRC requested e s"= nary of the site discussions. This was provided on March 2, 198c, Virginia Power personnel repeatedly stated that the use of pts is not necessary to verify post-modification functionality. It was stated that PT's could be used when appropriate; however, testing independent of the PT process could be performed to verify functionality.
Based on discussions with NRC SS0MI team members, their concerns, and previous Virginia Power reviews, Field Change 17 for DCP 87-12-2 135-BSD-71409-13 i
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'to revise the ER&SA and to add a Section 3.16 regarding functiona'l testing was approved by SNSOC on March 23, 1989. . Section 3.16 included the following:
"In order to perform this verification, testing will' be performed in
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accordance with the Final Design Testing Procedure. This test procedure.has been developed and modified based on testing recommendations included in Appendix 8-8 and functional checkout of the panel at the vendor' prior to shipment. . The existing circuitry shall be verified to not be. adversely affected by the installation of AMSAC by testing the circuit at least one contact or device upstream and one contract.or device downstream from the point at which AMSAC interrupts the existing circuit. This will be indicated by highlighting the elementary diagrams which are used in performing functional tests. These highlighted drawings will.be included in ~
the DCP as part of performance of the testing. The verification of the proper operation of the AMSAC panel'(including logic review) and verification of proper operation of components which change state when AMSAC is initiated, will also be verified in accordance with the functional testing performed per the Final Design Testing Procedure."
Also based on these discussions, Field Change 23 to increase the information re:orded during the testing of DCP 87-12-2 was prepared and was approved by SNSOC on March 31, 1989.
The testing performed and recorded for AMSAC should therefore adequately demonstrate no adverse impact on function of existing
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controls due to the installation of AMSAC.
- 3. 3. #, Virginia Power Position Post modification functional testing of AMSAC DCP 87-12-2 was performed in accordance with the final design test procedure and the testing as defined by Engineering in Section 3.16 of the ER&SA of the DCP. This did not require the post-modification 135-BSD-71409-14 L_ _ _
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performance of 2-PT-57.4 in order to verify functional response of the auxiliary feedwater pumps or the steam generator blow-down valves on an SI signal. This is true because Virginia Power uses testing within the DCP to verify testing and periodic tests (pts)
< are only used to perform this verification when deemed applicable, appropriate and timely.
The performance of 2-PT 57.4 was scheduled to be completed prior to February 23, 1989 per the pt schedule included as Reference 2 to NE-001 Rev. A. (Reference 5 4 of this document). Per telephone conversation with Mr. R. M. Garver on July 19, 1989, this PT and PT I-57.4 were performed at the beginning of each unit outage with the unit in Mode 4. Therefore, these tests were not run after the modification was completed.
4.0 CONCLUSION
S 4.1 Review of Response Virginia Power has made a good faith effort to respond to the NRC position as previously stated.
For Item 1 of finding IC-8, Virginia Power can provide reasonable assurance that testing has been adequately reviewed, performed and documented for all modifications performed under the DCP-EWR process. However, not all previously issued DCPs were updated to include a Section 3.16 on functional testing to the Engineering Review and Safety Analysis. This may mean that the NRC request has not been met in the manner that they intended, but did not clearly state.
For Item 2, Virginia Power can confirm the procedures have been updated. However, our organization is different than reflected in the NRC write up. Project Engineering is not involved on all DCPs and EWRs and therefore, does not provide the requirement on all such documents, though an appropriate party does. Implementation of 135-BSD-71409-15
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[ testing'is'donebyor.coordinatedbythetestengineerinvolvedwith
. the DCP. or EWR who. is in turn responsible to a site testing group.
L For Item 3, Virginia' Power did not perform the aforementioned' Periodic Tests after the installation of. the ATWS modification was-completed. = This is the ~ first formal written request for' this to be done and the unit has already restarted. However, Virginia Power can confirm that additional testing requirements and criteria were incorporated and that additional testing and documentation was.
incorporated into the Final Design. Test Procedure _to assure post-modification operation of systems which interface with the ATWS modification was not adversely impacted.
4.2 Review of Impact
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Item 1: M,ost DCPs were updated to incit;de a Section 3.16 to the ER&SA and those that did not have a change made were still reviewed.
Reopening'these DCPs to add a section 3.16 would require a post-fact effort which would be of little or no value.
The verification of-sequence of construction completion and testing for each portion of each DCP and each EWR has not been performed and is not recommended to be performed. This is true because existing methods of performing Ork provide significant assurance that testing was performed subsequent to the completion of the modification. Due to the large number of documents involved and the fact that documents are already reviewed by Quality, this effort appears exclusive.
Item 2: Virginia Power needs to make no changes to meet the NRC position here, other than explain our way of doing business.
Item 3: This testing cannot be done now to meet their desire that it be done prior to startup.
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However, the larger picture regarding this is that the NRC NRR personnel involved would generally prefer to see all refueling pts performed at the end of an outage after all modifications were completed. This would have a substantial impact on the outage plar.ning logic ard could impact the length of refueling outages by increasing the testing time period prior to startup.
This potentially significant impact should be considered before e decision on the basic issue is made.
5.0 REFERENCES
5.1 NRC to Virginia Power Letter Dated June 26, 1989.
5.2 NRC to Virginia Power Letter Dated March 17, 1989.
5.3 NE-001 DCP 87-12-2 (Functional Testing), Dated February 15, 1989.
5.4 NE-001 Rev. A, DCP 87-12-2 (Functional Testing), Dated February 16, 1989.
5.5 NE-001 Rev. B, DCP 87-12-2 Functional Testing, Dated March 2, 1989.
5.6 Station Administrative Procedure 3.7, " Engineering Work Requests",
Dated March 31, 1988.
5.7 Sthtion Administrative Procedure 3.7, " Engineering Work Request",
Dated May 26, 1988.
5.8 Station Administrative Procedure 11.1, " Design Change Test Procedure", Dated December 15, 1988.
5.9 Station Administrative Procedure 16.7, " Work Order Processing",
Dated November 11, 1988.
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5.10 Station Administrative Procedure 14.0, " Tagging of Systems and/or Components", Dated December 1, 1988.
5.11 Virginia Power Nuclear Design Control Program General Engineering Nuclear Standard, STD-GN-0001, Revision 8, Dated September 1, 1987 and Revisions.
5.12 Virginia Power Letter to NRC No.89-206 Dated March 31, 1989.
5.13 Virginia Power Letter to NRC No. 89-206B Dated April 28, 1989.
5.14 Virginia Power Letter to NRC No. 89-206D Dated June 30, 1989.
5.15 Permanent Procedure Deviation 89-002 Dated April 18, 1988.to Station Administrative Procedure 3.7, " Engineering Work Requests", Dated February 28, 1989.
5.16 Design Change Package 87-12-2, "ATWS Mitigation System Modification", SNSOC Approved November 10, 1988.
5.17 Design Change Package 87-12-2, Field Change 17 to Revise ER & SA, SNSOC Approved March 17, 1989.
5.18 Design Change Package 87-12-2, Field Change 23 to Enhance Testing, SNSOC Approved March 31, 1989.
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, Attachment 1 Unit 2 Outage - DCPs & EWRs. - DCPs Reviewed for Additional Functional Testing
UNIT 2 OUTAGE DCP's & EWR's DCP's REVIEWED POR ADDITIOREAL FUNCTIOllAL TESTING DCP. DESCRIPTICII 84-43 SW Header Tie-in - Rack Work FC - 69 noted 2-PT-36.11 85-08 ICCM System - T/ Couple Repair
& ICCM Cable Separation (FC 50) 87-29 CRDR -' Indicator Scale Changes 87-21 CRDR - Misc. Panel Mods. Included copy of completed 2-PT-82 H&I and 2-OP-6.5 to DCP 87-23 CRDR - SW & Recire. Spray CRDR - Press. Spray Valve Indicator 87-25 Lights 84-70 Press. Oven Installation / Rework 84-72 PSARY Belly Bands & Supports 86-10 Large Bore Snubber Replacement 87-12 ATWS FC Added Functional Testing To Blowdown TVs.
FD Pumps and PTS To Be Performed Prior To Startup 87-15 Feedwater Heater Replacement 88-12 RCS Level Indication 83-31 Gamma-Metrics - Cable Repair EWR 88-330 Charging Pump Air Binding EWR 88-329 Thermal Stresses - RCS Piping l
EWR 88-112 Replace SI Accumulator SOV's EWR 88-356 RS Pipe Replacement EWR 88-357 FW Pipe Replacement CRDR - Vital Bus Status Lights i EWR 88-100
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l UNIT 2 OUTAGE DCF's & EUR's I
DCF's REVIERD FOR ADDITI0 TEAL FUNCTIONAL TESTIEG f
DCF DESCRIPTION EWR 88-175& Condenser Inspections & Repairs EWR 88-176 EWR 87-673 Battery Charger Load Shed EWR 87-676 Raychem Verifiestion EWR 82-221A Installation of Key Lock Switches Postponed.
DCP 88-04 Rx Trip AT 30% Postponed DCP 88-16 2CN Pump Operation Without FWP Trip DCP 88-05 . (FC) 3RD Station Service Transformer. Non Outage DCP 89-02 Secondary Penetration Protection l-l l
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i Attachment 2 Unit 1 Outage - DCPs & EWRs --(DCPs Reviewed for Additional Functional Testing)
1 1 ...
LNIT 1 GJD M IKP'S/D8t'5 IXP/DR DESQtIPT104 88- 330A CHARGI!G PUW AIR O!!OI!G 84-71 PSARV BELLY BAIG #D HAN2RS88-202 000ENSER I!6PICrlO(88-201 GNE!NSER IACUllO REPIAQMINT 89-180 E.S. P!PE REPIACBelt 89-179 PW PIPE REPIAQMINT 89-01 SsW. IEAK REPAIR 84-89 PSARV OVB6 87-13 GPPER ALIM THE RMIX (F.W.
HIR. REPIACBENT)
- 88-11 BCS LEVEL IlOIC4rIOi 88-328 'IHES%L SIRESS - K3 PIPI)G 89-007 REP. SI A00.M. SOV'S 88-16 'DO G30. PU@ (PER.
85-07 IGN SYSI1N 88-01 MISC REYS. 'IO BEN 3 BOMB a ADEN.
85-29 REPL. BATHRY 1-BY-B-04 / REPL.
GNINI. St. BATERY OWZr REINN!RS 87-11 ADS 88-15 GN. OVERDCIT. PIUr.
84-43 SERVIG MA31R REUM NGB.
87-28 Out 1)CICA3GL SCAIR OWGS 87-21 UUt MISC. PANEL HGS.
413/ DES;oes
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l LNIT 1 GTDCE IXP'S/BR'S (PNE 2)
DCP/DR DES 0tIPTICN 87-24 G[R PRESSURIZER SPRAY VALVE I!OICATING LIGfrS 87-22 QUt SERVIG WA" . RIEllC. SPRAY
!aC MES.
86-09 LAR2 B3tE Sbinnet 89-258 INSPBCr #O REPAIR INIT 1 INDEE 1U NEL
!G-RB2NERATIVE HEWF EEHA!GR IRAIN LI!ES 413/ DES; des
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t Attachment 3 Unit 2 EWRs Reviewed 1
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. The following Engineering Work Requests implemented during the North Anna
, lit 2 Outage were reviewed:for appropriate source document control.-
The implementation and testing necessary for an EWR is controlled by k 'Section Maintenance procedures.as part of a Work Order.
4 Those EWR's not connected with a Work Order.were verified to. contain~ all -
th5 necessary steps of a stand alone document.
F 89-001 W.0L U1 & 2
'89-010 W.O.-
89-012- W.O.
89-013L W.0 89-014. W.O.89-025. W.O. UI & 2 89-027 S-A-DOC UI & 2 S-A-DOC UI & 2 89-028-fc9-028A S-A-DOC UI & 2 S-A-DOC UI & 2 J-028B
-- 89-028C .- - S-A-DOC - - - - - - - - - - - - - - .- -
UI &.2.- . . , .
89-028D S-A-DOC UI & 2.
89-028E S-A-DOC. U1 & 2 W.O. NON-0UTAGE 89-030 DWG. CRANGE 89-034 S-A-DOC NON-0UTAGE 89-036 S-A-DOC NON-0UTAGE 89-036A.
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EWRs. Reviewed May.1 through July 5, 1989.
7
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k SA -l 44 R9- 2)C f 29-24RR A M9 -A94. el
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l Attachment 5 EWRs Reviewed Between July 5 and July 12, 1989.
1 .
eUte.M .- b- h .
hioR wDa4m nm%Wam I l_t__d ~m Ay .%
$2F wLi* = 1hm l,__ - ' RQ -HIH O-T A)n A DD
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I .ta - o n c ,A fr ~
99 -oMD ti-i l 1. e s o en p S - To - O -O st$ir' 16-n 0-6 3 >* c I AJro 1-l-W ~ f-Mr R$r-i 6 04 0-6 v es i do / -/ W -#-AW
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L,
,. . Attachment 6 Memorandum July 14, 1989.from G. A. Rosetti to B.' S. Dunlap' dated 3
t
t XEROX TEl.Ecwic.n em i 7-so-2sa . 25 FWJ CCITT 03 + 80:2733448 ; o1
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, JL.A.' .14 '89 13:27 P.1/3 O Memomndum V)
Aprc'.21 ll.-
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- WuArv From OWtaMxistm '
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DCP/D R DESCRIPr!Of 88-330A G I4I C II C PLB @ AI R B17 0 H 0 ,
84-71 PSAltV BE!JX IWW ADO H49GIE .;
3 88-208 CD C H E R INBPICilOl'88-201 G3CaSR IAGmc IEPIX3mir 89-180 E.8. PIPE REPIA B elt 89-178 PW PIPE 117tXBett g 8.W. LEAIL NEPAIR , ,,
M-49 PEARV OVES h 87-13 GPPIB ALIN 113E ENIX (F.W. Sy mm. =rumme u ats IJms, aciocrias88-328 'DElt04L #M - E3 PIPDG 7 AEP. St AGDL SCW'8 emee. - m com. 'me cem.
85-07 IQ3881tsmi Y M, W3C. REYB.10 B808041D 6 ADIDE.
ks NEPL. BAlrIERY E=o. .m-r 1-BY-D.64 .r =m-. / EWL.
- > 2 KL16
% (BI. OVHBCIT. PIN.
@ sowim wmm asux mhs ') ;.
6 asa netoutz scar ones g ,' aim wse. Puer, m.
-are exaw,jde ,.o ,4 s s:a s.a L - - - - - - - - - - - _ - - - - _ - - - - - -
p, es vu ee p;c --~__m a r ..-
p,3,3 m.
LMIT l'Q1DG IXP'8/EhR'S (PAS 3)
DCP/ IDS !EBOLIPTIOf -
i, ,
" GER HEB8tRIFat 8 FRAY VAINE HelCArDC LIGt!5 L7 QER SWWIG m RE IE. SPRAY IaC KIS.
MD IAME EGE S m 39-254 IN Alt REPAIR IBilT 1 UtDER TutE
)OMEBMWrIVE IENT EERGER IRADI LIIe s
413/DE33 des. - - - - - - - - - - - - - - - - - - - -
4 i !
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.j Attachment 7 l
l, 1
Memorandum from S. L. Harvey to D. A. Heacock dated i March 29, 1989. 1 ec ;
l 1
I i
l i
I i
. e MEMORANDUM i
TO ' -D.A. Haacock North Anna Power Station FRC44 S.L. Harvey March 29, 1989 l RESPONSE TO CTS ITEM NUMBER 02.89.2164/007 (SH-024)
A. All DCPs and EWRs being implemented during the Unit 2 outage were reviewed te ensure the following functional criteria is met.
- 1. Installed modification operational logic of the circuit is as intended by the design change.
- 2. Installed modification does not after the operational logic of any other system input to modified circuit.
- 3. The modified circuit output operational logic is the same as before unless it was altered by the design change.
The functional testing is to be performed by the testing section of the DCP. The functional testing will be verified to at least one point upstream and one point downstream of the unaltered part of the modification. Additional testing being performed such as startup test and periodic test that will be performed by normal startup procedure will be listed in the acceptance criteria section as an enhancement to the overall functional testing.
B. Section IIIB.2 DCP 87-12 ATWS 1.- Additional testing will be added to the functional testing sections of the following components to ensure criteria in A is met and documented.
- a. TV-BD-200A-F
- b. TV-SS-212A & B
- c. 2-FW-P-3A & B
- 2. Additional Periodic Tests will be added to the acceptance criteria section.
- a. 2-PT-71.1 2-FW-P-2 operational lineup
- b. 2-PT-71.2 2-FW-P-3A operational lineup
- c. 2-PT-71.3 2-FW-P-3B operational lineup
- d. 2-PT-71.4 Auxiliary Feed Pump Logic Test
- e. 2-PT-34.4 Turbine overspeed Protection
- f. 2-PT-36.1A & B Reactor Protection and ESF Logic Test
- g. 2-PT-36.7.2 Rsactor Trip from Turbine Trip
- h. 2-PT-213.1 Steam Generator Blowdown valves operational test
+
- 1. 2-PT-213.10 Sample System valve operational test
?[5?,'s~$---
a: l
-mmp -
- a; ~%.
w
- C.. Review DCP's awaiting implementation for- -
additional testing.
- 1. . Additional testing and documentation has been added to the following.DCPs.
' s.- DCP 84 FC 69 added' functional testing
~ documentation and included 2-PT-36.11 (Emergency Bus degraded Voltage, loss of voltage response time test) to meet criteria A.
- b. DCP 87-21 added documentation showing 2-PT-82.2 2H&WDiesel runs ' will be . performed after the
-modifications are complete'in the Control Room and 2-OP-6.5 will be performed in the 2H diesel room to shown operability of the diesel panel after modifications are complete.
S.L. Harvey SLH/jas 8
c--p a .- eww ee+,e> e e w,e e - m***-- *-+4e+- *** *'N* ** 9 ****'****'*"~~## * * *'
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-_.__.=_____-_-_ -__ - - _ -
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Attachment 8
. Memorandum from S. L. Harvey.to D.'A. Heacock dated May 4, 1989.
l'
- I.
l l'
V b .- _ _ - . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
~., ,
l - [, .
MEMORANDUM L
L TO D.A. Heacock North Anna Power Station FROM S.L. Harvey May 4, 1989 RESPottSE TO CTS ITEN NUMBER 02.89.2164/008 (SH-023)
A. Attached is a list of EWRs implemented during the Unit 2 outage and to be implemented during the Unit 1 outage which have been reviewed. All EWRs to be implemented in the future will be reviewed for additional testing requirements prior to implementation.
B. The attached list of DCPs to be implemented during Unit 1 outage were reviewed and the following changes will be made.
- a. TV-BD-100A-F
- b. TV-SS-112A & B
- c. 1-FW-P-3A & B
- a. 1-PT-71.1 7-FW-P-2 operational lineup
- b. 1-PT-71.2 ).-FV-P-3A operational lineup
- c. 1-PT-71.3 J.-FW-P-3B operational lineup
- d. 1-PT-71.4 Auxiliary Feed Pump Logic Test
- e. 1-PT-34.4 Turbine Overspeed Protection
- f. 1-PT-36.1A & B Reactor Protection and ESF Logic Test
- g. 1-PT-36.7.2 Reactor Trip from Turbine Trip
- h. 1-PT-213.1 Steam Generator Blowdovu valves operational test
- i. 1-PT-2[RJO Sample System valve operational test
- 3. Additional testing and documentation has been added to DCP 84-43. FC 69 added functional testing documentation and included 1-PT-36.11 (Emergency Bus degraded Voltage loss of voltage response time test).
- 4. Additional documentation showing that 1-PT-82.2 (1H&lJ Diesel runs) will be performed after the modifications will be added to DCP 87-21. Additional documentation showing that 1-OP_6.5 (1H diesel remote operation) has been performed showing operability of the diesel panel after modifications have been completed.
S.L. Harve Il'O9. ,Wa%,
a
%. ,e Virginia Power Action hSTD-GN-0001 will be revised " icequire documentation on all testing being performed, not only on the r tfication, but on all systems interfacing 006 with the modification. Acti . ' PES Nuclear - Knutsen 4/15/89.
Q A11 design rackages awaiting implementation at North Anna will be co ~l reviewed a 4 field changed as required to identify the tests being oot performed in affected systems. Action: PES Site - Harvey -
Unit 2 - 4/07/89, Unit 1 - 5/05/89.
i
@ A field change will be generated to include a failure analysis in the ATWS package. . Action: PES Project Engineering - R. W. Riley 3/31/89. Od Imssons Learned Although advisory operations has been preparing an adequate comprehensive test matrix, all testing requirements must be documented well in the design package. Requirenwents are rapidly increasing in this area. A comprehensive evaluation should be documented in each package to assure existing system functionality is not altered.
C N 13 di IIIC. DCP 84-43 Service Water Modifications .
An example was cited.where non-IE equipment was installed in a safety cabinet without adequate isolation. The non-IE enuipment was procured IE, but installed non-IE. Resolution of this item is a restart issue.
Virginia Power Action
.p $ The example cited on package 84-43 will be'modifie6 to provide adapate O / D
} IE- non-IE isolation. A PPR will be generated to document this I condition. Action: PES ItC - McBride 4/1/89.
(
h A review will be performed on other packages awaitis.g implemer,tating to 08/
address any generic implications. Action: PES I&C - McBride 4/07/89 - o f 2.
Unit 2; 5/05/89 - Unit 1.
Nors:
'Itseem tuo items emot be completed prior to returning either unit to service.
14seems Imarned Practices whi:h were acceptable in the past are no longer able to withstand current scrutiny. Although new installation may meet the requirements of original equipment, the responsible engineer must analyze and document the need for equipment upgrade on a case by case basis.
IV. EI2CTRICAL COMPONWTS, The reviewers indicated that progress has been made in our M.O.V.
programs however, there is much more to be don *, particularly with old 135-RWR-4190-5