ML20129A865

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Summary of 850510 Meeting W/Util,Bnl & S&W in Bethesda,Md Re Resolution of Remaining Open Items & Issues Resulting from NRC Sqrt/Pvort Audit.List of Attendees,Slide Presentation & Sser Responses Encl
ML20129A865
Person / Time
Site: River Bend Entergy icon.png
Issue date: 05/17/1985
From: Siegel B
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8506050001
Download: ML20129A865 (100)


Text

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,% g UNITED STATES 3 g NUCLEAR REGULATORY COMMISSION

$ j WASHINGTON, D. C. 20555

%..... MAY 171985 Decket No. 50-458 APPLICANT: Gulf States Utilities Company FACILITY: River Bend Statict

SUBJECT:

SUMMARY

OF MEETil!G TO RESOLVE OPEN ITEMS AND ISSUES RESULTING FROM THE NRC STAFF SQRT/PVORT AUDIT AT RIVER BEND STATION A meeting was held between the hRC staff and Gulf States Utilities Company (GSU) on May 10, 1985 in Bethesda, Maryland to resche the renaining open itens and issues resulting from the staff SQRT/PV0F.T audit at River Bend Staticn (FBS). Enclosure 1 contains a list of n;eeting attendees.

The generic aspects of the RBS program for seismic and dyr;anic qualification of safety related equirnent were discussed by L. Schell of GSU. Enclosure 2 contains ccpies of vu-graphs used by L. Schell. Enclosures 3 and 4 contain specific responses to tFe dettiled findings of the SQRT/PVORT cudit (October 29, 1504 through November 2,1984) that were identified in the audit report sent te GSU by letter dated January 20, 1985.

The status of each of the specific responses which required resolution was discussed during the meeting and the resolution of each issue or iten is summarized below. In some instances supplemental docuracntatien was provided to the staff and its ccr.sultant Brookhaven National Laboratory during the neeting to cbtain resolution.

Issue or Iten Resolution B0P-3, Findinc 1 Supplcnental information provided by GSU for staff review. If information adequate issue will be resolved.

60P-3, Finding 2 Response acceptable, resolved.

BOP-3, Finding 3 Response acceptable, resolved.

BOP-4 Response acceptable, resolved.

B0P-8, Finding 1 GSU approach for resolution acceptabic, hkC will review documentation provided to determine acceptability of appli-cation. If documentation provided acceptable issue will be resolved.

B0P-8, Finding 2 Response acceptable, resolved.

80P-8, Finding 3 Pesponse acceptable, resolved.

B0P-8, Findire 4.1 Response acceptable, resolveo.

80P-8, Finding 4.2 Response acceptable, resolved.

BOP-8, Fincing 4.3 Response acceptable, resolved.

BOP-9 Response acceptable, resolved.

B0F-10, Finding 1 Documentation provided by GSU has to be g506050001850517 R

A ADOCK 05000458 PDR

p: y reviewed. If docunentaticn provioed consistent with conclusion presented during meeting issue will be resolved.

-B0F-10, Finoing 2 Resolution same as for BOF-10, Finding 1.

hSSS-1, _

' Response acceptable,_ resolved.

I;SSS-2, Finding'1 Response acceptable and resolved if coct.tentation provided includes safety margin and test results fcr control console panel including bolted section.

NSSS-2, Finding 2 Resolved if GSU provides confirmation

? that bottom control console panel support greater than 1/4 inch thick.

'NSSS-2,'Firdirc S /.pproach acceptable as presented -durirc meeting. GSU to revise response, reference documents, and samples. PescIved if infortation to be provided acceptable.

L l;SSS-3 Response acceptable, resolved.

liSSS-S, Finding 1 Resolved as presented by GSU during.

raeeting. 6SU to revise response to specify panels used have same dimensions-and structural characteristics as those tested except for the width.

NSSS-5, Finding 2 Response acceptable, resolved.

FSSS-5, Finding 3 Response acceptable, resolved.

I;SSS-5, Finding 4 Response acceptcble, resolved.

liSSS-E, Finoing 5 Response acceptable, resolved.

liSSS-5, Finding 6 Responst. acceptable, resolved.

14555-6 Resperse acceptable, resnived.

NSSS-7, Firfirc 1 Ccsolved as presentea by 6Sb derii.9 meeting. Revise response tc state transnitters werc qualified in the aged condition.

'NSSS-7, Finding 2 Response acceptable, resolved.

NSSS-8, Finding i Response acceptable, resolved.

I;SSS-8, Finding 2 Response acceptable, resolved.

hSSS-8, Finding 3 Response acceptable, resolvad.

-The eight generic open issucs identified in our January 30, 1985 letter to the -

applicant were also discussed with GSU. Based en the information provided curing the neeting the staff deterrired r.c additional information was required from the applicant except for tvic generic issues that- required confirmatory information. GSU stated their confirmatory responses to these issues would be provided by Jure 1, 1985.

Following the discussicns the staff caucused to deteruine if c followup audit would be perforr:cd. The staff infonned GSU that no follevtup audit would be performed hci.cVer GSU was requested to select two systems end perform their cwn mini-audit. GSU was infortec' this nini-audit should be perforn,ec end the results

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reported to the NRC ' prior to exceedir.g 5% of rated power. In a follchup telephone conversation on liny 13, 1085 GSU was infomed that their. prcposed

-prograta for the 't.iini-audit should be subnitted to the staff-for review anc-l approval prior to fuel load erd e letter of consnitment should be provioed to

-the staff.

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yron Si el, Project Manager Licensing Branch No. 2

-liivision-of' Licensing

Enclosures:

As stated

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report'ed_to the NRC prior to exceeding 5% of rated' power. In a folicwup telephone /conversationion llay-13,1985 GSU was informed that their proposed-aprogran'for-the mini-audit should be submitted to the staff for review and 1 approval prior to fuel load and.a letter of 'comitment should be provided to Ethe' staff.

Byron Siegel, Project Manager Licensing Branch No. 2 Division of Licensing

Enclosures:

. As stated-cc: -See next page--

Distfibution:

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-NRC PDR-

' Local PDR' PRC System NSIC-LB#2 Reading

' Dewey,-_ OELD WButler-DWagner EHy1 ton SStern

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. L8' 2 fPM L/Pri - LB#2 DL/BC

'tBSi et:lb SS rn WButler

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'hr. William J..Cahill, Jr. .

River Berd-Nuclear Plant Gulf: States Ltilitics Corpany cc: Troy 6. Cor.ner, Jr. , Esq. Ms. Linda B. Watkins/ltr. Steven-Irving Conner and Wetterhchn . Attorney at Law-

-1747 Pennsylvonic Aver.ue, h. W. 355. Napoleon Street

-Washington, D.C. 20006' Baton' Rouge, Louisiana 7CE02 Mr. 'Willian J. Reed, Jr.

Director - Nuclear Licensing Culf States Utilities Company Post Office Box 2951-

- Beaumont , Tens 77704 Ik. David-Zaloudek Nuclear-Er. orgy Division H. Anne Plettingei Louisiana Department of 3456 Villa Rost Cr. Environmental Quality Boten Rouge, Louisiana 70806 Post Officc Cox 14690 Baton Rouge, Louisiana 70050 Richard H. Troy, Jr., Esq.

. Assisttnt Attorney General in Charge StLie of Louisiana Departri.ent of Justice "

224 Lcycla-Avenue hew Orleans, Lcuisiana, 70112 Mr. J. David fictieill, III Dwight D. Chericriain William G. Davis, Esq.

Resident Inspector Cepartment of Justice Post Office Box lubl Attorney General's Office St. F rarcisville, Louisiana 70775 7434 Perkins kcao.

Peten Rouge, Louisiana 70808 Gretchen R. Rothschild Louistonians for Safe Energy, Inc.

1659 Glerrrerc Avcr.ue

. Baton Rouge, Louisia.a 707)5 Jancs .U. Pierce, Jr., Esq.

P. O. Box 23571 Batcr. Rcuse, Louisiana 70893 Mr. Robert D. Martin U.S. NRC, Ecgior. IV' Parkway ~ Central Ple u builcing 611 Ryan Plaza Drive Sutie 1000 Arlington, Texas 76011 V

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Encicsur] 1 ECUIPMENT-QUALIFICATION llEETII'G blikliER BEhD 1 BAY.10, 1965 NAl1E - 'AFFILIATIGN Byron Siegel hRC/DL/LB-2

? John G. Propson GSU Gcutam Bagchi. -NRR/DE/EQB R.-J.~Bosuck URC/DE

h. D. Romney ._ . NRC/DE/EQB

~Kamal-Bandyopadhyay Bhl

~Rudy Hoder ' Ghl

J. E. Booker ~ GSU - Hgr. Engr 6 :lic. .

K. M. Skreiner .Nutech Consultant to GSU.

R.~W. Haroy CE E. Earl Hichols CE N. G. Lurit GE J. J. Boseman GE-D. K. Henrie GE

-kick J. King GSU/ Licensing-Ret Piht , SUCC 4 Narendra Muni SUEC-Arie'Litu S!!EC coseph C.-Bisti SUEC Laurentiet Sct. ell G50 Judy Mancil GSU Lar ryi Rctscer. GSU Leif_Dietrich- SULC F..A. Cartsc St.EC

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  • Enclosure 2' RIVER BEND STATION PROGRAM-FOR SEISMIC AND DYNAMIC QUALIFICATION OF SAFETY RELATED EQUIPMENT NRC REVIEW MEETING 5/10/85

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r 3 O PART I FORMAL PRESENTATION

.c s INTRODUCTION O PURPOSE OF THIS MEETING IS TO PROVIDE ADDITIONAL INFORMATION REQUESTED BY THE.NRC FOLLWING THEIR SQRT/PVORT AUDITS SINCE THE APPLICANT CONSIDERS THE PRESENT GE AND SWEC ACCEPTANCE REVIEW PROCEDURES ADEQUATE, DESPITE THE PROBLEMS NOTED BY THE AUDIT TEAM, THE APPLICANT IS TO PROVIDE ADDITIONAL INFORMATION TO REINFORCE HIS POSITION AND ASSURE THE STAFF THAT THE CONCERNS DISCOVERED DURING THE AUDIT ARE NOT REPRESENTATIVE OF THE PROGRAM." IECHNICAL EVALUATION REPORT, BROOKHAVEN NATIONAL LABORATORY, APRIL 23, 1985.

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OBJECTIVE l.

To-demonstrate'that the findings generated by the SQRT/PV0RT are not indicative of programmatic deficiencies.

To present-the results of the GSU review of the nature of the SQRT/PV0RT findings.

1R) provide the bases and Justifications supporting the conclusion that programmatic deficiencies do not. exist.

To present the GSU concept for. orderly transition of aualification effort.

To discuss GSU responses for the remaining open issues.

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CURRENT DIVISION OF QUALIFICATION EFFORTS General Electric Company Qualification for equipment within the NSSS scope of supply Stone & Webster Engineering Corporation Qualification for equipment within the B0P scope of-supply Installation and preliminary testing of all equipment

v SQRT/PV0RT PROGRAM ELEMENTS Procurement / Qualification Specification Qualification Standards Qualification Requirements Review / Approval of qualification documents

QA Requirements Identification of Deliverables Installation Specification Physical Installation Verification (FQC)

Preliminary Testing Functional Installation Verification Pre-operational and Acceptance Testing Functional Installation Verification on a Subsystem and System Basis Surveillance and Maintenance Verification of Continued Operational Readiness l

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PROGRAM STATEMENT

- The programs used by'GE and SWEC establish qualification.

.These programs were found acceptable on similar NT0L plants.

  • GSU is developing on action plan for orderly transition

- of the qualificotton effort from GE'ond SWEC, 1 e T

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.e GSU REVIEW 0F SQRT/PVORT FINDINGS Review' detailed comments for indications of programmatic deficiencies.

Group comments by categories.

. Provide detailed explanation and demonstrate that findings are not indicative of generic problems.

. Provide back-up documentation not available at audit.

Provide detailed analysis to support engineering Judgement questioned by reviewers.

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CATEGORIES OF NRC COMMENTS

. Clarification

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An explanation of procedures, specifications, data, tags, etc was not readily available during the audit.

Documentation Documents referenced in the-aualification'recorts were not immediately available at the audit.

Detail.

' Additional proof of-Judgements made in establishing qualification was requested by the reviewer.

Installation Equipment was physically in place, however, final F0C inspection and^ acceptance and pre-operational and/or start-up testing.was not yet performed.

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CATEGORIZATION OF 10/84 SQRT/PVORT AUDIT FINDINGS SQRT PVORT Total Findings' 32 27 Classification i Clarification 16 25 2

. Documentation _ 6 -

c Detail 7 1 Installation 3 1

,First Round Responses Accepted-by NRC 19 23 (18 subject to review

.of documentation) y<D L'

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RESULTS ALL NRC CONCERNS HAVE BEEN ADDRESSED BY GSU.

A PROGRAM WAS INITIATED T0 IDENTIFY MAINTENANCE /

SURVEILLANCE REQUIREMENTS FOR ALL SAFETY-RELATED EQUIPMENT. THE REQUIREMENTS WILL BE IMPLEMENTED INTO THE APPLICABLE GSU PROCEDURES.

AN ACTION PLAN IS BEING DEVELOPED FOR ORDERLY TRANSITION OF THE QUALIFICATION EFFORT FROM GE AND SWEC TO GSU.

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"3 CONCLUSIONS ~

. MOST FINDINGS REQUIRED.

ADDITIONAL BACK-UP DOCUMENTATION ADDITIONAL BACK-UP ANALYSES TO SUPPORT ENGINEERING JUDGEMENT

. THE REVIEW. SUPPORTS A CONCLUSION THAT FINDINGS ARE NOT INDICATIVE OF GENERIC PROGRAMMATIC DEFICIENCIES

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GSU ACTION PLAN PURPOSE TO PROVIDE AN ORDERLY TRANSITION OF THE QUALIFICATION EFFORT FROM GE AND SWEC TO GSU.

METHOD DEVELOP GSU PROCEDURES FOR TURNOVER OF QUALIFICATION DOCUMENTS.

ESTABLISH ACCEPTANCE CRITERIA FOR COMPLETENESS OF DOCUMENTATION.

ASSIGN AND TRAIN DEDICATED PERSONNEL FOR THE REVIEW 0F QUALIFICATION PACKAGES TO THE ACCEPTANCE CRITERIA.

GSU SIGN-0FF AND APPROVAL 0F FINALIZED PACKAGE.

DEVELOP GSU PROCEDURES FOR FUTURE EQUIPMENT QUALIFICATION.

6 EXECUTIVE

SUMMARY

STATEMENT THE RIVER BEND STATION QUALIFICATION PROGRAM IS BEING EXECUTED BY GENERAL ELECTRIC (GE) AND STONE a WEBSTER ENGINEERING CORPORATION (SWEC) ON THE BEHALF 0F GULF STATES UTILITIES (GSU). A DETAILED GSU-REVIEW 0F THE NATURE OF THE FINDINGS GENERATED BY THE NRC SQRT/PV0RT AUDIT DEMONSTRATES THAT PROGRAMMATIC DEFICIENCES DO NOT EXIST. THE BASES AND JUSTIFICATIONS FOR THIS CONSLUSION WERE PROVIDED IN THIS PRESENTATION, GSU WILL CONTINUE THE QUALIFICATION EFFORT CURRENTLY BEING PERFORMED BY GE AND SWEC AND IS DEVELOPING A PROGRAM FOR AN ORDERLY TRANSITION OF THE QUALIFICATION EFFORT.

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  • Enclosure 3 1

PART 11 s

X-NRC/GSU/GE/SWEC REVIEW 0F RESPONSES TO DETAILED FINDINGS t

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SQRT (Total Findings: 32)

Clarification Documentation -Detail Installation NRC Accepted

'NSSS-1 X NSSS-2(1) X (2) X (3) X NSSS-3 X D NSSS-5 (1) X (2) X

-(3) X

.(4) X D (5) X (6.a) X D (6.b) X /

NSSS-6 X D NSSS-7(1) X D (2) X D NSSS-8(1) X D (2) X D

-(3) X D BOP-3 (1) X D (2) X (3) X D

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(4) X D BOP-4 (1) X D (2) X D (3) X D BOP-8 (1) X D (2) X (3) X (4) X BOP-9 (1) X D SOP-10(1) X D (2) X 16 6 7 3 1+18D 13

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PVORT.(Total Findings: 27)

Clarification Documentation Detail Installation NRC Accepted

  • NSSS-5(1) X NSSS-7 (1) X (2) X

/ l (3) X (4) X .-

(5) X

/

BOP-6 (1) X (2) X /

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(3) X

/

(4). 'X (5) X. /

BOP-9 (1) X /

/

-(2) X V

(3) X (4) X

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(5) X

/

(6) X

/

BOP-12(1)- X (2) X /

BOP-13(1) X v

(2) X

/

(3) X (4) X /

BOP-SURPRISE (1) X /

.(2) X /

(3) X /

B0P-11 (1) X /

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT-ID No.: BOP-3 Applicant ID No.: IEHS*MCC15B Finding No. 1 Qualification of devices apparently covered by Gould Reports R-STS-16 and 31 and analysis was not available for review.

Response

Seismic qualification of motor control center 1EHS*MCC15B is covered by Gould reports:

R-STS-16 R-STS-25 R-STS-31 SC-289 All these reports, with the exception of report SC-289, have been claimed

~ by Gould as proprietary and as such could not be produced for the NRC's review. Report SC-289 is the Gould seismic certification report, which was- approved by SWEC on October 27, 1984 (reference SWEC File No. 4242.562.082.002E, attached). This report contains seismic qualification of the MCC enclosure and 24 of the 30 Class IE devices.

Proprietary report R-STS-25, qualifying the HE43 circuit breaker, was reviewed by SWEC on May 23, 1984, and the results were accepted. Report SC-289 and SWEC's trip report on R-STS-25 were made available to the NRC auditors. .

Proprietary Reports R-STS-16 and R-STS-31 contain qualification results for the remaining five Class IE devices. Based on, (i) Gould's use of SWEC approved test procedure, (ii) Gould's certification of the qualifi-cation results of the remaining five devices in Report SC-289, and (iii)

Gould's demonstrated capability to provide an acceptable qualification program, results of these five devices were accepted without an RBS-specific review of Reports R-STS-16 and R-STS-31. This acceptance baris was discussed by the SWEC engineer with the NRC reviewer during the audit.

It should be pointed out that the same SWEC engineer had previously reviewed Report R-STS-16 and many other Gould proprietary reports for other SWEC proj ects . Some of the reviewed reports are listed below:

C4/12210/555J/4YH 1

Gould Report No. Wyle Report No. Date Reviewed R-STS-11 42926-1 July 12, 1983 R-STS-16 43472-1 August 22, 1983 R-STS-23 44519-1 May 23, 1984 R-STS-33 45483-1 May 23, 1984 GSU had also informed the NRC during the preaudit discussions that some proprietary documents would not be available to the NRC during the audit.

Instead, if the NRC found it necessary, special arrangements could be made with Gould for the audit of these documents.

Seismic qualification analysis of terminal blocks and power resistors was made available for the NRC review. This analysis is contained in Sec-tion 4.0 of Report SC-289. This analysis was based on a comparison of the terminal blocks and power resistors installed in RBS with those tested along with 24 other devices listed in Table 1 of Report SC-289.

SWEC had evaluated the adequacy of this combined analysis and testing approach during the review of Report SC-289 and found it to be acceptable, considering the passive nature of the devices (see Telemecanique letter dated April 1, 1985, attached).

Corrective Action Gould proprietary Reports R-STS-16 and R-STS-31 were subsequently reviewed by SWEC on November 28, 1984, to reconfirm compliance. Results were found to be acceptable and are documented in the attached SWEC File No. 4242.562.082.003A. With respect to the RBS terminal blocks and the power resistors qualified by combined analysis and testing, no further action is deemed necessary.

Conclusion Since the NRC reviewer believed that Reports R-STS-16 and R-STS-31 should be reviewed, SWEC proceeded with this review. The judgment of the original SWEC reviewer to accept these documents without review was proven to be correct.

GSU believes that the original course of action pursued by the SWEC reviewer was appropriate and justified.

C4/12210/555J/4YH 2

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: BOP-3 Applicant ID No.: 1EHS*MCC15B Finding No. 2 Test mounting was not documented.

Response

Test mounting details are shown on page 76 of Gould Report SC-289, SWEC File No. 4242.562.082.002E (attached). This report was made available to the - NRC during the audit. As a result of the NRC. question, Gould has reconfirmed that the welding details on page 76 of Report SC-289 reflect test mounting condition (reference: Gould Electronics letter dated February 27, 1985, attached).

Corrective Action Not applicable.

Conclusion This finding only required reconfirmation of the information presented at

.the audit.

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C4/12210/555K/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: BOP-3 Applicant ID No.: IEHS*MCCISB Finding No. 3 It is not clear from the test report whether the MCC was tested for five OBEs and one SSE for both the energized and deenergized conditions.

Response

'The MCC was tested for five OBEs and one SSE in both energized and deenergized conditions. This information was compiled through SWEC's review of several Gould proprietary MCC qualification documents listed in the response to Finding No. 1.

In each of the tests covered in the above reports, the equipment was tested in both energized and deenergized conditions during the five OBE and one SSE tests. Confirmation of this test condition was requested and received from Gould through a letter dated February 27, 1985 (attachment).

Corrective Action Not applicable.

Conclusion

This - finding required furthez; clarification of information presented at

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,the audit. The results of the original qualification review performed by SWEC remain unchanged.

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C4/12210/555L/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 .

SSER TABLE 3.10.1.1 SQRT ID No.: BOP-3

, Applicant ID No.: 1EHS*MCC15B Finding No.-4 Supplemental evaluation report for HE43 circuit breaker was not part of the qualification documentation package.

Response

The supplemental evaluation referenced in the finding was included as part of the SWEC-prepared qualification review summary. The text of this evaluation was intended as an aid to the SWEC reviewer in completing the review and was not intended to become an addendum to the vendor's qualification report.

The NRC reviewer believed, however, that this information should be included as part of the. vendor's report. Accordingly, SWEC has included this information in the qualification documentation package (reference attached SWEC File No. 4242.562.082.003A).

, GSU believes that the data contained in Gould Reports SC-289 and R-STS-25 provide an adequate basis for qualification of the HE43 circuit breaker.

Corrective Action Not applicable.

Conclusion The addition of the SWEC supplemental evaluation to the vendor prepared

. qualification package is an enhancement to the original data provided by Gould and has no impact on the seismic qualification of the HE43 circuit breaker.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: BOP 4 Applicant ID No.: IE12*PC003 Finding The site inspection revealed the following deficiencies:

1. The shim stack was loose.
2. One nut in the seal housing was loose, and another was missing.
3. The motor nameplate was missing.

Response

During the NRC site inspection, the NRC questioned the reason for the reject tag affixed to the subject pump. Unsatisfactory quality assurance inspection report (IR) Type A M4000947 dated October 24, 1984, was pre-sented to the NRC to explain the rejection. This normal inspection was accelerated for the NRC audited item. The Unsat IR lists five deficient conditions including those listed above. A copy of the inspection report is attached for reference.

l As can be seen from the IR, the loose shim stack problem applies to pump l 1E12*PC003, the pump included within the scope of the audit. The IR also l identified deficiencies with an additional pump, IE51*PC003 (loose nuts, i missing nameplate), which was not included within the original audit scope. The deficiencies ,for pump IE12*PC003 were corrected on October 26, 1984, prior to the NRC site inspection, in association with Construction Work Request (CWR) No. 4545 (attached). However, because the work associated with pump 1E51*PC003 had not been completed, the Unsat IR remained open and the REJECT tag remained affixed to pump IE12*PC003. SWEC's QA program requires all deficiencies on any Unsat IR l- to be corrected prior to removal of any REJECT tags associated with the l IR. -The conditions cited by the NRC in the audit report were those noted l by the Inspector on the SWEC Unsat IR. All deficiencies noted on the l Unsat IR have now been corrected.

l Corrective Action None required.

C4/12210/555/4YH I

Conclusion

'The condition cited above, and documented on SWEC Unsat IR prior to the~

NRC audit, provides another example demonstrating that an effective quality assurance program exists on the River Bend Project, which results in detecting and tarrecting deficiencies.

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C4/12210/555/4YH 1

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: BOP-8 Applicant ID No.: ISCM*XRC14 Finding No. 1 Dynamic similarity between the tested specimen and the River Bend trans-former was not established.

Response

The vendor seismic qualification report (SWEC File No. 6244.512.271.008A) did not clearly establish dynamic similarity between the tested specimen and the River Bend transformer. Although characteristic transformer parameters were compared to establish similarity, no natural frequency comparisons were performed. SWEC commented on this during the normal

, review process on October 24, 1984, and requested that the vendor provide additional dynamic data. The Seismic Qualification Master List, submit-ted to the NRC prior to the audit,. indicated that the transformer was not as.yet fully qualified (status shown was " test complete but test report not: approved").

SWEC therefore performed a calculation to estimate the natural frequency of the River Bend equipment. The result, together with the vendor evalu-ation cited above, convinced SWEC that similarity did exist.

(_ Corrective Action l At SWEC's request, the vendor provided additional information to i

establish similarity. The additional information, together with the SWEC l calculation, was documented as part of the review of the vendor's .re-l submittal of the -seismic qualification report, and the report was i approved on March 21, 1985 (SWEC File No. 6244-512-271.008F, copy l attached).

Conclusion The concern noted in the finding had 'been identified by SWEC through the normal SWEC review and approval process in accordance with the SWEC

, equipment qualification program and procedure, and the seismic qualifica-l tion of the device was not considered complete until the SWEC concern was resolved.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: BOP-8 Applicant ID No.: ISCM*XRC14 1

i Finding No.-2 1

Test mounting was not completely documented in the test report.

Response

Wyle test report No. 58733 states that the seismic test of Model No. 253-1-101 was performed in accordance with Elgar's Seismic Test Plan Document No. 543-288-92 and that "the test specimen was attached to the test fixture in a manner that simulates normal in-service use" (refer-ence SWEC File No. 6244.512-271-008A, Appendix N, pages 3,.4, and 2-1, attached). Elgar's Test Plan 543-288-92 requires that the specimen be 3

attached to the test machine in a manner that simulates normal in-service

attachment, as shown on Drawing No. 543-288-71 (reference SWEC File No. 6244.512-271-008A, Appendix P, page P-3, attached).

Based. on these statements, it is concluded that the equipment was welded to the test fixture in a manner similar to that shown on Elgar Drawing No. 543-288-71, attached. 1

No other documented evidence of test-mounting condition is readily 4 available. .Since the qualification test was sponsored and managed by

-Elgar as part of its generic program, GSU did not have any control over

the degree of mounting details which were included in the test documents.

. It should be noted that River Bend equipment Model No. 503-1-1 is quali-fied through its similarity to Model No. 253-1-101 (also see Response to i Finding No.1). Model No. 503-1-1 has a slightly different base than Model No. 253-1-101, and therefore the mounting weld details are differ-ent. Justification and reconciliation of the differences between the base of these models are discussed below. '

Elgar-recommended installation details for Model No. 503-1-1, shown on I '

Drawing No. 7481014-02 (attached), are 4 1/4-in. fillet welds, 2 in.

long, and 4 1/4-in. fillet welds, 4 in. long typically. at each corner.

-River Bend installation, shown on Drawing No. 0244.512-271-005D, provides 4 1/4-in. combined flare-fillet welds, 5 in. long, and 4 1/4-in. combined

+

flare-fillet welds, 1 in. long at each corner. Adequacy of the River l-C4/12210/555U/4YH 1

J Bend weld installation was verified through Calculation No.12210-SEG-STRU-S-E82(27), Rev. 1 (attached), dated June 3, 1983.

This calculation also demonstrates structural adequacy of the base plate.

Adequacy of the base with respect to stiffness was assumed using en-gineering judgment.

The seismic test results (reference SWEC File Nos. 6244.512-271-008A through F) indicate that the equipment is rigid, i.e., in > 10 Hz. Since the River Bend installation is adequate to meet the Elgar requirements, it was concluded that the River Bend installation would result in a rigid installation equivalent to the vendor's installation drawing. Based on this result, and the natural frequency of 12.2 Hz based on analysis, it was further concluded that the equipment dynamic response due to seismic loading would not change as a result of the differences in the installa-tion details.

Corrective Action To satisfy NRC's concern about possible introduction of flexibility as a result of the use of the base plate, a frequency analysis of the trans-former-base plate assembly was performed. Results of this analysis (Calculation No. 12210-NM(C)-SQE-2101 (attached)) indicate about 5-percent reduction in the fundamental frequency with the introduction of the base plate. The fundamental frequency reduced from 12.2 Hz to 11.6 Hz, which is higher than 10 Hz, and, therefore, the previous con-clusion of rigidity remains unchanged.

Conclusion This concern was found to have no effect on River Bend qualification, since an independent verification of the adequacy of the River Bend installation had been addressed.

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C4/12210/555U/4YH 2

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.:- BOP-8 Applicant ID No.: 1SCM*XRC14 Findina No. 3

~

Test anomalies were mentioned, but neither described nor justified in the test report.

Response

A thorough review of the test report presented to the NRC during the audit reveals no mention of anomalies recorded during or as a result of the test. Following NRC identification of this concern in the SSER, the vendor was requested ' to provide - a response and also indicate if any anomalies were observed during the test (SWEC File No. 6244.512.271.008F, copy attached.)

Additionally, copies are attached of referenced Report No. 80202,

page 11, and the applicable data sheets, which clearly do not list any anomalies.

Corrective Action Not applicable.

Conclusion Based on all available documentation, no anomalies were observed during the test program. .

C4/12210/555V/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: BOP-8 Applicant ID No.: ISC!t*XRC14 Finding No. 4 Site inspection revealed the following:

1. There was no contact between the base plate and concrete in most places.
2. Side panels were loose.
3. Base plate was not addressed in the qualification documents presented.

Response

It is GSU's understanding that each of the above findings were responded to and resolved satisfactorily during the audit. Responses provided to the NRC reviewer during the audit for each of the findings are as follows:

1. SWEC inspected the equipment on November 1, 1984, and found the base plate properly mounted to the floor with no gaps. Photo-graphs taken during the inspection on November 1,1984, indi-

! cating no gaps, were provided to the NRC on November 2, 1984.

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2. This equipment was undergoing preoperational testing at the time the NRC inspected it. The side panels were removed and put in place temporarily during this test phase, explaining the I looseness. Quality Assurance Inspection Report No. E440927 l (attached), which was issued to monitor the testing being con-ducted, was provided and discussed with the NRC on November 2, 1984. Work is still in progress.

, 3. The base plate is considered to be part of the floor support l system and, therefore, is not addressed in the equipment quali-

! fication documentation.

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[ Design adequacy and structural integrity of the base plate is addressed in Structural Engineering Calculation No. 12210-SEG-STRU-S-E82(27), Revision 1, dated June 3, 1983 l

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C4/12210/555W/4YH I

(SWEC File No. 6244.512-271-008F, attached). Also see response to Finding No. 2 of BOP-8 for additional discussion.

Corrective Action None required.

Conclusion Based on the responses given, it can be concluded that findings similar to the above are normally detected and corrected by programs in place at

. the site or substantiated by existing calculations. Therefore, no pro-grammatic deficiencies exist.

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C4/12210/555W/4YH 2

I 'RBS-EQUIPMENT QUALIFICATION PROGRAM i

SSER RESPONSES a.

RIVER BEND STATION - UNIT 1

, DOCKET NO. 50-458

SSER. TABLE 3.10.1.1

, SQRT ID No.: BOP 9 j Applicant ID No.: IEJS*LDCIA Findina i

Only a summary of the test report was available. The original Wyle Test Report is needed for review and documentation.

Response

The Powell Electric Manufacturing Company Qualification Report No. 0984-J.O. No. 12210-QR, Revision 0 (SWEC File No. - 4242.533-265-005A),

which was reviewed and approved by SWEC on October 15, 1984, contains

- results of a seismic test performed by Wyle Laboratories. The test results - were relevant ' data considered by SWEC during the review of the Powell qualification report. The SWEC reviewer considered the test re-sults to be credible information and did not believe it was necessary to review the Wyle seismic test report before completing the review / approval of the Powell qualification report.

Corrective Action A copy of the Wyle seismic test data was obtained at the request of the

, NRC reviewer. This data was reviewed by SWEC and found to be consistent-with the information provided in the Powell qualification report-and documented under SWEC File No. 6242.533-265-012B (attached).

, Conclusion .

The SWEC reviewer of the Powell qualification report believed that suf-ficient information was available to complete the qualification report review / approval without reviewing the Wyle seismic test data. This ,

judgment was subsequently proven to be correct.

GSU believes . that since Powell qualified the equipment in question utilizing an approved 10CFR50 Appendix B QA program and certified that the qualification report results were correct and accurate, the SWEC reviewer acted prudently and correctly in this matter.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: BOP-10 Applicant ID No.: ISWP*P2B Finding No. 1 Torsional frequency of assembly needs to be computed and compared to motor's operational speed.

Response

It is SWEC's conclusion that torsional frequency would be of no concern for this pump, since it is a constant speed pump with a solid coupling between the motor and the pump shafts. However, as the result of the NRC reviewer's concern, the pump manufacturer, Hayward Tyler Pump Company, was contacted for its position on this issue. The manufacturer indicated that it has never experienced torsional frequency problems with its pumps. It should be noted that the pump was operational at the time of the audit with no evidence of problems of this type. The industry telies more on the functional test of the pump to identify and correct any resonance problems than on analytical data.

Corrective Action

To comply with the NRC request concerning a possible torsional resonance problem, the torsional natural frequency of the pump assembly was cal-culated and compared to the operating speed (reference: SWEC Calculation No.12210-NM(C)-SQE-2073, attached). The operating speed of the pump is 1180 rpm, and the calculated, torsional frequency is 828 rpm, which is 29.8 percent lower than the operating speed. This exceeds the 25 percent margin recommended by the Hydraulic Institute (reference: Hydraulic Institute Standards for Centrifugal Rotary and Reciprocating Pumps, Hydraulic Institute, 13th Edition, 1975).

Conclusion The qualification review and approval process, in combination with test-ing conducted as part of the preoperational test program, is considered adequate to identify and correct any problems of this nature.

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C4/12210/555E/4YH

RBS-EQUIPtfENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: ' BOP-10 Applicant ID No.: ISWP*P2B Finding No. 2 Operability of pump under seismic load needs to be ensured.

Response

=The program for ensuring operability of pumps and motors under seismic loads is described in the River Bend FSAR, Subsection 3.9.3.2.1A.

The following documents, supporting pump operability, were submitted during the audit:

SWEC File Nos.

4232.920-257.001B, C 0232.920-257-018B, -019C, -020B 0232.920-257-021A, -022A 6232.920-257-001B, -002C, -003B 6232.920-257-004C, -005D 6232.920-257-006A, -008A i

NRC reviewer's concern about the effects of building displacement and thereby the pump support displacements due to seismic loading was already factored into the seismic loads used in the qualification.

A small relative displacement at the pump supports, excluding that due

,to the rigid body rotation of the building, was anticipated.

Since the specification and the qualification analysis of the pump under seismic load considered 40-percent higher seismic loads than the River Bend requirements, effects of the relative displacements were more than adequately addressed.

Corrective Action As a result of the NRC's concern over the effects on pump operability due to building displacement, an analysis was performed to calculate the responses in the various pump critical - components. Results of this analysis (reference SWEC Calculation No. 12210-NM(c)-SQE-2100, attached) indicate that:

C4/12210/555AS/4YH 1

o- 'O

1. The building displacements at all the pump supports are in phase due to seismic loading.
2. The resultant pump column stress is increased by approximately 500 psi, 'which is less than 10 percent over the previously calculated stress of 5,200 psi, and compares with an allowable stress of 27,000 psi.
3. Stress in the pump shaft is increased by approximately 95 psi, which is less than 1 percent over the previously calculated stress of 10,560 psi, and compares with an allowable stress of 31,500 psi.
4. The maximum load on the bearing is increased by approximately 13 lb, which is less than 3 percent over the previously calculated load of 448 lb.

Conclusion The use of 40 percent higher than the required seismic loads in the pump qualification analysis more than adequately accounts for the building relative displacement.

9 C4/12210/555AS/4YH 2

I NSSS SQRT - SSER F

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t 9 RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1-SQRT ID No.: NSSS Applicant ID No.: 511-D001

' Finding The additional brace used during qualification testing of the equipment was missing from the installed unit.

Response

The seismic qualification test on the hydraulic control unit (HCU) was performed to an SRV fatique RRS that significantly exceeds the RBS requirements. As the result of this very conservative test, a hanger holding the N2 bottle on the HCU broke. Analysis of. the hanger attributed the _ failure to fatigue. The test specimen was modified by replacing the broken hanger and adding a second brace to the . unit, which reduced the deflection of the hanger, and the test was continued and successfully completed. -

Since the RBS RRS for SRV fatigue is significantly less severe than the tested RRS, RBS decided not to add a second brace to the HCU brace -

already installed but to analyze the fatigue load on the hanger using RBS specific requirements. The analysis demonstrated acceptability of the hanger for a lifetime in excess of 40 years. To establish dynamic similarity between the test unit and the RBS installed unit, a finite element analysis was performed which demonstrated that there was no significant difference in the dynamic response of the units. In GSU's judgment, this analysis, in conjunction with the fatigue analysis of the bottle hanger, was sufficient to justify applicability of the test data on the double-braced test specimen to the single-braced RBS HCU. The above analyses were presented to the NRC reviewer during the audit, and -

although 'the fatigue analysis was accepted, the reviewer requested further proof of dynamic similarity which would have required GSU to refine the three-dimensional computer model of the HCU and perform additional analyses.

Instead, GSU elected to pursue an alternate approach of qualifying the '

HCU to a limited life using the test data accumulated on the single-braced test unit prior to failure of the hanger. This approach is described in the attachment and was provided to the NRC in GSU's previous response - to SSER open items (reference RBG-20594 dated March 29, 1985).

C4/12210/555AF/4YH I

.- IL In response to an additional question raised by the NRC following the review of the information presented above, the following is provided.

The design basis for RBS (BWR 6) postulated 1,800 SRV actuations over the life of the plant (reference RBS FSAR 6A.17.2.4) . Each SRV actuation results in approximately seven pressure oscillations (reference FSAR Figure A.6A.5-13) equivalent to three fatigue stress cycles (total of 3 x 1,800 = 5,400 cycles). The qualification report for the HCU states that the 15 minutes of SRV fatigue aging subjected the test specimen to an excess of four times the number of required fatigue stress cycles (reference NEDC-30820, Vol 1, p 14).

_ Corrective Action.

None required.

Conclusion This concern was found to have no effect on River Bend qualification.

GSU's conservative approach qualifies the HCU for a limited life, at the expiration of which the units will be refurbished, as required, under the RBS maintenance / surveillance program.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458

.SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-2 Applicant ID No.: H13-P680 Finding No. 1 The dynamic similarity between the test specimen and the River Bend equipment shall be demonstrated in order- to utilize the existing test

- results.

Response

The SQRT qualification report that was presented to the NRC reviewer during the audit states the RBS panel as assembly Drawing No. 914E519.

The subtier RBS drawing for the center console is 914E541. The tested panel 'is Drawing No. 865E499 (reference DRF No. A00-1138-T). These drawings were' available at the- audit. The criteria used by GE in

, establishing dynamic similarity for RBS between tested and installed units have been utilized for . other plants, discussed with the SQRT reviewers, and found acceptable in previous audits at the following plants:

Susquehanna March 1981 Shoreham April 1981 1 Grand Gulf July 1981 Hanford November 1982 Limerick January 1984 Perry July 1984 The same procedures were used for RBS. The SQRT reports for the above plants included a written discussion of these criteria. The correspond-ing writeup was omitted from the RBS package. The writeup will now be added to the RBS SQRT report.

The RBS control console (H13-P680) consists of a center section, which is structurally similar to the tested center section, and two wing sections.

The two wing sections were not tested but are structurally similar to the midsection of the center section. The addition of the wing sections, which are bolted to the center section (reference Drawing No. 944E109),

stif fens the console assembly and provides for a reduced dynamic response as compared to the center section alone.

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C4/12210/555AG/4YH 1

Corrective Action

-A writeup outlining the criteria used to establish similarity between tested and installed panels will be added to the SQRT report.

Conclusion.

Dynamic similarity between the tested and the installed panel was

- established using criteria that were found acceptable for other NTOL plants.

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I C4/12210/SSSAG/4YH 2

g- .L RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER-TABLE 3.10.1.1 SQRT ID No.: NSSS-2 Applicant ID No.: -H13-P680 Finding No. 2-The test mounting should be completely documented in the test reports and compared with the inservice mounting for acceptability.

. Response.

The test report states that "in the field, the console is welded with 1/4-in. by 4-in, welds to the PGCC frame at each angle on the base.

Since this could not be done on the seismic table, clamps were used at each weld location." (

Reference:

DRF No. A00-1138-T, Item 5.0.) The field mounting is specified in Drawing No. 944E109 and shows two 1/4-in.

by 4-in. welds for each corner of the console assembly.

Corrective Action i

None required.

Conclusion The test mounting is representative of the field installation. This con-cern was found to have no effect on River Bend qualification.

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C4/12210/555AB/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SS'ER RESPONSES RIVER BEND STATION - UNIT 1

, DOCKET NO.' 50-458 SSER TABLE 3.10.1.1 SQRT ID No. : NSSS-2 f

Applicant ID No.: H13-P680 E

Finding No. 3 For devices qualified separately, the complete test report should be

!. available to define the capability g-values and to de:nonstrate that the RRS is enveloped over the entire frequency range.

'~

Response

, Complete test reports for devices qualified separately were made avail-able to the NRC reviewer during the SQRT audits. The reports express the equipment capability in terms of g-values based on single-frequency test-ing. The methodology for arriving at these g-values is described in RBS FSAR Section 3.10.2.2B. While single-frequency testing is generally not used to establish qualification in accordance with IEEE 344-1975 and Regulatory Guide 1.100, IEEE 344-1975 and the GE SQRT program permit the use of such test data for devices under any of the following conditions:

' 1. . The device input notion is dominated by one frequency.

[ 2. The device is rigid, or its response is adequately represented by'one mode.

3. The device can be characterized as passive, in which case its safety function is satisfied by maintaining structural

[ integrity. ,

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4. The device is similar to another device that has been tested to IEEE 344-1975 requirements.

l l S. The device was tested to a sufficiently high acceleration level

( to excite all modes over the frequency range of interest.

The above criteria were used in the GE seismic qualification reevaluation l program for each of the six projects previously audited and accepted by the NRC SQRT (see 'SSER response to SQRT ID No. NSSS-2, Finding No.1).

i The same criteria were used for RBS.

1 l The capability g-values are compared to the required accelerations at the

! equipment mounting location. These are obtained as the product of the C4/12210/555AI/4YH 1 l.

4 ,.-- -- __w _y . ,yy .y... . - . v. .,7 .-, 9 ,

w ,--y- - , . - = ,,

maximum panel traasmissibilities measured at the mounting location at the panel resonance and the ZPA of the applicable RBS floor response spectra.

GE has performed studies to show that this .is a very conservative approach to determine maximum required accelerations.

Corrective Action None required.

Conclusion The qualification for devices mounted in control room panels was established using the same criteria 'that were found acceptable for other NTOL plants.

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.- C4/12210/555AI/4YH 2

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1 SQRT ID No.: NSSS-3 Applicant ID No.: C61-P001

.Findine The installation condition of being next to another cabinet and the wall was not addressed in the qualification.

f

Response

SWEC originally located panel C61-P001 (documented on E6DCR No. P-2772) as directed by the ability to locate anchor bolts within the reinforcing bar

' pattern of the concrete floor. No specific clearance criteria were provided by GE for the panel in question prior to installation.

l Corrective Action In order to resolve this issue in a timely fashion and to support the NRC audit, GE was contacted and asked to aid SWEC in evaluating the clearances provided for the panel in advance of work completion in the area where the panel is located. E&DCR Nos. C-68,908 and P-2772D have been issued as a result of the evaluation. These change documents will result in rework of the subject panels. - E&DCR No. C-68,908 incorporates GE FDDR LDI-3021, Revision 1

!: and Revision 2. As dicteted by GE, the two panels are being bolted together to eliminate the gap betieeen the panels. Work is currently being performed as j authorized by Rework Cor. trol Form E-7154 Additionally, specific guidelines for panel to panel clearances will be added to the SWEC Electrical Installation Specification. These clearances will be evaluated after installation is completed via SWEC Construction Site Instruction (CSI) 81.1 which requires that a walkdont he conducted for purposes of performing this evaluation. Differences noted during the walkdown are resolved by engineering or rework as appropriate.

i Conclusion 1

The corrective action stated above will ensure that similar conditions are precluded in the future.

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RBS-EQUIPMENT QUALIFICATION. PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 i

'SQRT ID No.: NSSS-5 3

Applicant ID No.: H13-P601 Finding No. 1 Dynamic similarity between the tested specimen and the RBS unit was not established.

Response- ,

i The SQRT qualifict. tion report that was presented to the NRC reviewer dur-ing the audit states the RBS panel as assembly Drawing No. 914E501. The subtier RBS drawing ' for the panel is Drawing No. 914E594. The tested panel is comprised of the right two bays of the production unit, Drawing No. 865E118AB (reference to DRF No.' A00-1138, Tab I, Section 4.0). Since the bays are lined up in a s':raight line, testing of a smaller number of bays as coepared to the plant installation produces representative re-sponses in the front-to-back and vertical directions. The side-to-side responses are reduced in the plant installation since additional bays, bolted together, provide additional stiffness.

The criteria used by GE in establishing dynamic similarity for RBS be-tween tested and installed units have been utilized for other NTOL plants, were discussed with the SQRT reviewer, and were found to be ac-l ceptable. The SQRT reports for these plants include a written discussion

[ of these criteria; however, such a writeup was omitted from the RBS pack-age. The writeup will now be added to the RBS SQRT report.

-Corrective Action A writeup outlining the criteria to establish -similarity between tested and installed panels will be added to the SQRT report.

Conclusion Dynamic similarity between the tested and the installed panel was estab-lished using criteria that were found acceptable for other NTOL plants.

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C4/12210/555AJ/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-5 Applicant ID No.: H13-P601 Findina No. 2 The test mounting should be completely documented in the test report and

-compared with the as-built configuration for acceptability.

-Response Photographs of test mounting contained in DRF No. A00-1138, Tab I, and General Electric (GE) base mounting detail Drawing No.133D9825 indicate that the test specimen was secured to the seismic table using all avail-able mounting holes in the front and rear base plate members. The mount-ing detail shows these bolts at I ft 0 in. on center.

The installed RBS panel is mounted to the PGCC floor via 1/2-in. bolts on 6-in. centers. The installed RBS mounting gives a much stiffer ' base, yielding a lower seismic / dynamic response characteristic. Therefore, the tested panel accelerations are considered conservative when applied to the RBS case.

The NRC's consultant followed this response with the comment that a com-plete description of the test mounting shall be included in the test re-port (bolt: number, diameter, spacing, grade, etc; weld: type, size, length, spacing, grade, etc).

The following reviews were performed to address the followup question.

As stated above, the spacing for the hardware for mounting the test specimen to the table is 1 ft 0 in. centers. This is shown on the refer-enced drawing, which also shows the holes for the hardware to be of 3/4 in. diameter. This is consistent with GE's practice of using 5/8-in.

~ diameter bolts to match the predrilled and tapped holes in their shake table surface.

-In the initial evaluation, engineering judgment had been employed to con-clude that the RBS installation structural integrity was adequate. In order to support this engineering judgment, the following analysis is provided.

An analysis of tested and installed bolt stresses was made in the re-sponse to the NRC's finding for SQRT ID No. NSSS-6. The same analysis l

C4/12210/555BD/4YH 1 l

is applicable for this panel, which was mounted during the test using 5/8-in. diameter bolts at I ft 0 in. centers, while the inservice instal-lation used 1/2-in. diameter bolts at 6-in. centers. The analysis con-cluded that the stresses in 1/2-in. bolts would be 80 percent of the 5/8-in. bolts for the same loading on the tested and installed panel.

The TRS/RRS ratio for this panel is approximately 89.5, which means the inservice installation stresses would be (1/89.5) or 1.1 percent of the tested stresses for the same size of mounting bolts. The combined effect of twice the number of 1/2-in. bolts installed to 5/8-in. bolts tested would make the inservice 1/2-in. bolt stresses (0.80)(1/89.5) = 0.9 per-cent of the stresses in the 5/8-in. bolts tested.

This clearly illustrates that the installed mounting is adequate, since it is very conservative.

Corrective Action None required.

Conclusion The documentation describing the test mounting was reviewed, and it was confirmed that the as-built configuration is acceptable with a high degree of conservatism.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1

. DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-5 Applicant ID No.: H13-P601 Finding No. 3 For component qualification, the capability g-values were not defined and demonstrated to envelop the RRS over the entire frequency range.

. Response Same as NSSS-2, Finding No. 3 Corrective Action None required.

Conclusion The qualification for devices mounted in control room panels was estab-lished using~ the same criteria that were found acceptable for other NTOL plants.

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C4/12210/555AX/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-5 Applicant ID No.: H13-P601 Finding No. 4' Qualification of some devices below 5 Hz was missing.

Response

All optical isolators, square rc,ot extractors, controllers, CR2940 switches, and Cutler - Hammer switches have been tested for resonances below 5 Hz and have been found to have none. These devices were the only devices for which qualification below 5 Hz was missing. Meters are of the galvanometer type and are not subject to resonances below 5 Hz, al-though some needle movement may occur, which has no effect on safety.

The NRC's consultant followed this response with the further request that the response needs to . be verified with the qualification documents.

The following qualification documents were reviewed to address this ques-tion:

Device Document Controller A00-l'084-176, Index D

' Square Root Converter A00-1084-135, Index C CR2940 GE Switch A00-1084-58, Index E Optical Isolators ,

A00-794-21, App. E Cutler Hammer Switches A00-1084-95, App. E These documents support the original response that no resonances exist below 5 Hz.

Corrective Action None required.

Conclusion The absence of resonances below 5 Hz was verified in a review of the qualification documents.

C4/12210/555AZ/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT I DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-5 Applicant ID No.: H13-P601

' Findina No. 5 Controller and recorder units were sliding during the test. It could not be verified 'from documentation presented whether the River Bend panel contair.s these devices.

. Response Movement of several controllers and recorders was observed during the test of prototype panel H12-P870 (prototype for panel H13-P601). These various components were ' tested on prototype panel H12-P870 only as a matter of convenience. River Bend control room panel H13-P601 has only one of these components, controller 163C1392. This controller continued to_ function during the test of prototype panel H12-P870, in spite of the movement observed. The ZPA of the TRS exceeded the RRS by a- factor of six. It was concluded that no additional requirements need to be ~placed on production panels, since normal procedure following a seismic event requires inspection of all safety-related equipment. .

Corrective Action None required.

Conclusion This item does not affect .the qualification of the panel. The operability of the- controller was successfully demonstrated, especially in light of the significant margin applied during testing.

4 f

C4/12210/555AY/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM

.SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-5 Applicant ID No.: H13-P601 Finding No. 6 Site inspection revealed the following:

1. One unistrut was loose.
2. GE ERIS terminals were very flexible.

Response

1. Inspection Report (IR) No. E4300485, dated November 1, 1984 (attached), identifies unistrut supports recorder E12-R601 as having a loose mounting. Since this _IR was initiated prior to turnover to construction, a CWR was not required, and the unistrut bolts were tightened to the torque values specified in Specification No. 248.000, Revision 8. FQC verifies that the actions were com-pleted in accordance with the required specification.
2. The ERIS system is classified as non-Class IE. Due to their very small weights, the ERIS terminal blocks would not become missiles during any seismic events and thus would not jeopardize any other Class IE equipment on this panel.

Corrective Action None required.

Conclusion Implementation of Electrical Inspection Plan No. R1248000F05240B02 would -

have identified this loose unistrut. However, the implementation of the electrical inspection plan was not complete r' the time of the NRC audit, and hence, the loose unistrut was not identified as such.

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C4/12210/555AP/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO.-50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-6 Applicant ID No.: 1H13*P670

-Finding The cabinet was installed with 1/2-in.-diameter bolts, although the specimen was tested with 5/8-in.-diameter bolts.

Response

Cabinet 1H13*P670 is installed on floor module 1H13*U710 in accordance with General Electric (GE) Drawing No. 914E989, sheet 1, Revision 5 (SWEC 3

File No. 0242.426-000-422E). 1H13*U710 assembly floor sections D-D and J-J (reference GE Drawing No. 914E962, sheets 1 and 2, Revision 2, SWEC File No. 0242.426-000-451B/452B) identify the mounting studs arrangement and reference the material as Part No. 3. GE Parts List PL914E962, Revi-sion 2 (SWEC File' No. 0242.428-000-507B), calls out Part No. 3 as 1/2 in. - 13 x 1.62 Lg Stud. Therefore, the studs were installed by the manufacturer in accordance with GE-approved drawings.

The tested panel was mounted using 5/8-in.-diameter bolts at 12-in.

centers, while the inservice installation used 1/2-in.-diameter bolts at 6-in. centers. In the initial evaluation, engineering judgment had been employed to conclude that the RBS installation structural integrity was adequate. In order to support this engineering judgment, the following is provided.

The bolt stresses are controlled by tensile area and shear (gross) area

~~ o f the bolts. The tensile areas for 5/8 in. and 1/2 in, are 0.226 sq. in. and 0.142 sq in., respectively. The gross areas of 5/8-in, and 1/2-in. bolts for shear are 0.307 sq in, and 0.196 sq in. , respec-tively. The i.est and inservice panel mounting critical areas are as follows:-

Ratio of Stress, Inservice Tested Inservice vs Tested Tensile Area 0.226 0.284 0.8

'(sq in.)

C4/12210/555AC/4YH 1

Ratio of Stress, Inservice Tested Inservice vs Tested Shear Area 0.307 0.392 0.8 (sq in.)

From this comparison, the stresses in 1/2-in. bolts would be 80 percent of the 5/E-in. bolts. The TRS/RRS ratio for this cabinet is approxi-mately 37.5, which means that the inservice installation stresses would be (1/37.5) or 2.7 percent of the tested stresses for the same size of mounting bolts. The combined effect of twice the number of 1/2-in. bolts installed to 5/8-in. bolts tested would make the inservice 1/2-in. bolt stresses (0.80) (1/37.5) = 2.1 percent of the stresses in the 5/8-in.

bolts tested. This clearly illustates that the installed mounting is adequate since it is very conservative.

Corrective Action None required.

Conclusion As outlined above, the 1/2-in.-diameter bolts are adequate to withstand the imposed loads. -

r C4/12210/555AC/4YH 2

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-7 Applicant ID No.: H22-P041, 42 Findina No. 1 Transmitters were ~not environmentally aged prior to seismic testing.

-Response' Aging of the transmitter was performed in a separate environmental and qualification test. It was determined that aging had no effect on the seismic qualification of the device (reference DRF No. A00-01312-20).

Based on this information, the data presented at the audit is adequate to demonstrate qualification.

Corrective Action None required Conclusion The effects of aging are addressed as documented in DRF No. A00-01312-20.

C4/12210/555BA/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-7 Applicant ID No.: H22-PO41, 42 Finding No. 2 Transmitter output varlation was detected during testing, apparently due to incomplete instructions provided by GE to testing engineers regarding calibration.

GSU/GE is to confirm that River Bend installation engineers have received complete instructions and that the transmitters are properly calibrated.

Response

Complete Rosemount adjustment and calibration instructions have been defined to the RBS installation engineers for proper calibration. In addition, GSU calibration procedures, such as Procedure No. MCP-4067, Rev. O, dated August 6, 1984, Calibration of Rosemount Model 1152 Transmitter, provides detailed ' calibration instructions which are based on vendor manual GEY 5577, Volume 3, Tab 22 and SWEC Manual No. 3242.414-000-006A.

Tested devices were identical to RBS devices or have been analyzed to be similar (reference DRF No. A00-901-002 and VPF No. 442X711-001, sh. 20).

The NRC's consultant followed this response, with the further request that the documents through which these instructions have been conveyed should be made available to the SQRT for review.

The relevant document, vendor manual GEY 5577, Volume 3, cited above, was conveyed from GE to SWEC and GSU via Transmittal No. 2969 during the 33rd week of'1983, as evidenced in the attached transmittal summaries.

Corrective Action None required.

Conclusion It is evident from this response that existing RBS programs are effec-tively implementing necessary equipment adjustment and calibration pro-cedures.

C4/12210/555AL/4YH

, : - . 7, RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BIND ',70. ION - UNIT 1 DCCKE'" N?. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-8 Applicant ID No.: B21-F022/F0283 MSIV Finding No. 1 4

Adequacy.of the valve body was not demonstrated.

Response

The MSIV body, ' yoke assembly, and actuator are modeled in the piping analysis, which is performed using 3-dimensional finite element dynamic analysis. GE Specification No. 213A8418 (attachment) summarizes-the data required to model the valve and also its loading capabilities. Piping analysis performed and reported in Stress Reports 23A4062, 4063, and 4064 (related pages attached) dated May 1, 1984, documented and compared the dynamic pipe-induced loads at the valve body (locations G1, G2, and F) against the maximum allowables. Since the induced loads are less than

. the maximum allowed, the adequacy of the valve body is demonstrated.

Corrective Action None required.

Conclusion Based on the response provided above, GSU confirms that the adequacy of the valve body was demonstrated prior to the NRC audit.

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w RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND-STATION - UNIT I DOCKET NO. 50-458

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SSER TABI.E 3.10.1.1 SQRT ID No.: NSSS-8 Applicant ID No.: B21-F022/F028B MSIV Findina No. 2 GSU should confirm compliance with GE's recommendation regarding the following required for qualification:

1. Bracket modification for limit switch
2. Elimination of junction box

Response

Bracket modification for Ifmit switches and elimination of junction boxes are initiated - via GE's FDI No. 76/56800, Revision 0, dated August 23,-

1984 (attached).

Corrective Action >

None required.

Conclusion Based on the above response, GSU confirms the compliance with GE's recom-mendations regarding bracket modification for Limit Switches and elimina-tion of junction boxes for MSIVs. The actions needed to confirm the compliance with GE's recommendations were initiated by GSU prior to NRC L audit, l'

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ge a RBS-EQUIPMENT QUALIFICATIGN PROGRAM SSER RESPONSFS RIVER BEND STATICN - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.1.1 SQRT ID No.: NSSS-8 Applicant ID No.: B21-F022/F028B MSIV Finding No. 3 The source of River Bend specific RRS was not presented during the audit.

Response

River Bend Station specific RRS for dynamic testing of the MSIV were calculated by the GE Piping Analysis Group No. II, transmitted to the MSIV responsible engineer by memo - Nguyen to Nieh dated February 15, 4

1984, and provided to the NRC auditors in response to the question raised during the audit (attachment). -

Corrective Action None required.

Conclusion .

Based on the above response, GSU believes that the source of Riier Bend specific RRS was available and presented to the NRC auditors.

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. RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-6 i

Applicant ID No.: ICCP*MOV138 Findina No. 1 Valve has serial number 809 (1980) on "N" stamp tag. Manufacturer's nameplate serial number is 1413-2. PVORT form lists valve serial number

as 809 (1980). Inspection and test record form list serial number as 1413. Clarification required.

Response

The PVORT form provided to the NRC at the time of the audit listed the valve S/N 809 (1980). The valve manufacturer includes two serial numbers for the valve, a valve S/N and a body S/N. For the subject valve, l

S/N 809 is the serial ' number for the valve and S/N 1413 is the serial number for the valve body. Exclusion of either S/N from-the PVORT form would -not degrade or impair the effectiveness of the RBS PVORT program.

I- The use of the manufacturer's nameplate serial number. is recorded on i inspection and test records to distinguish between the valve manufacturer and the supplier of the valve body's forging or casting.

Corrective Action The PVORT form has been revised to include both serial numbers (see attachment).

i .-

Conclusion .

The PVORT forms were prepared at the request of the NRC for its use to aid in the review of the specific equipment included within the audit scope.

Retrieval of pertinent qualification documentation to substantiate the equipment's ability to perform its intended safety function is controlled

-via the unique mark / identification number attached to each piece of equipment, i.e., ICCP*MOV138. GSU believes that omission of one of the serial numbers from the PVORT form has no impact on the qualification of the equipment in question.

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i C4/12210/555F/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-6 Applicant ID No.: ICCP*MOV138 Finding No. 2 Stroke time requirements need clarification; they vary from 30 seconds (specification sheet) to 22 seconds (inspection and test record) to 20 seconds (PVORT forn).

Response

Stroke time for this valve is 20 seconds. This time is stated on the PVORT form. During the review of the documents, the NRC reviewer looked at the valve data sheet from Revision 1 of the specification (attached),

showing 30 seconds as the required stroke time for the valve. A SWEC engineer clarified that the data sheet had been revised in Addendum No. 2 to Revision 1 of the specification, and the current data sheet (attached) shows the 20-second stroke time, which is consistent with the PVORT-form.

The discrepancy regarding the stroke time on the inspection and test record was clarified during the audit, and the correct record (attached) showing the 20-second stroke time was presented to the NRC reviewer.

Corrective Action None required.

Conclusion This concern was resolved with the NRC reviewer during the audit. The applicable documents are attached to further clarify that a consistent stroke time of 20 seconds is stated on all three items in question.

C4/12210/555G/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-6 Applicant ID No.: ICCP*MOV138 Findina No. 3 Have stem leakoff requirements been provided?

Response

The subject valve was provided with a stem leakoff connection in accord-ance with the valve technical data sheet included -in SWEC Specification No. 228.212. A short length of 1/2-in., schedule 80 pipe connected to the valve body is provided, as shown on the Velan Company valve drawing (SWEC File No. 0228.212.047-008L). This connection is not used on River Bend and therefore is not piped up to a permanent drain point. The leak-off is to be plugged in accordance with applicable requirements provided in Piping Erection Specification No. 228.160 and on the installation drawing. A photograph of the stem leakoff connection was provided to the NRC inspector during the audit.

Corrective Action None required.

Conclusion Stem leakoff provisions for this valve are consistent with engineering l requirements documents. SWEC design procedures require piping up valve I- stem leakoffs for high-pressure and/or high-temperature applications only, and this valve does not fall into this category.

i C4/12210/555H/4YH l'

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT I DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-6 Applicant ID No.: ICCP*MOV138 Finding No. 4 Have space heaters been removed?

Response

Space heaters, located inside the limit switch compartment of MOV oper-ators, had failed in some specimens during the River Bend dynamic test program. The nature of the failure did not affect the operability of the

' actuator. During the discussion of this failure, GSU informed the NRC reviewer that these space heaters do not perform any safety function and that they would either be disconnected electrically or removed altogether after placement of the valves in service. SWEC had already addressed this issue in a letter to GSU, SWEC Letter No. RBS-9515 dated June 13, 1984.- GSU has subsequently decided to electrically disconnect the heaters. E&DCR No. C-60,849 dated February 14, 1985 (attached), provides direction to disconnect the heaters.

Corrective Action E&DCR No. C-60,849 has been issued.

Conclusion GSU believes that this finding highlights the fact that the River Bend QA l

program is controlling the engineering and design process effectively.

This issue had been identified by CSU/SWEC prior to the audit.

i C4/12210/555D/4YH

RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES

? RIVER BEND STATION - UNIT 1 1

DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-6 Applicant ID No.: ICCP*MOV138 Finding No.5 Revision 2 to MOV Checkout Procedure 1-G-EE-18 was initiated due to ex-cessive . torque values in Revision 1. Comparing Revisions 1 and 2, the torque values appear to be the same.

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Response

Revision 2 of 1-G-EE-18 added a note which allowed the use of socket-head or hex-head fasteners to facilitate torquing. The original slotted-head fasteners were stripping during tightening, which precluded the applica-tion of the required torque values. The intent of the revision was not to reduce the torque values (and, in fact, it did not reduce torque values), but to change the type of fastener head utilized. It should be noted that Revision 7 of Procedure 1-G-EE-18 was the effective revision at the time of the NRC audit.

Corrective Action Not applicable to this finding.

i Conclusion No followup or preventive action is required as a result of this item.

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i RBS-EQUIPMENT QUALIFICATION PROGRAM 4

'SSER RESPONSES RIVER BEND STATION - UNIT 1 l- DOCKET No. 50-458 SSER TABLE 3.10.2.1 ,

PVORT ID No.: BOP-9 4

Applicant ID No.: IE33*SOV14 Findina No. 1 Valve installation contradicts Note 18 of FSAR Figure 6.7-1, qualifica-2 tion documentation and stsnufacturer recommendations.

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- Response l

i This discrepancy has been investigated and determined to be caused by a misinterpretation of the required direction of flow which occurred during j

the ~ design process. This, in turn, resulted in the incorrect valve orientation being shown on the drawings. The key design documents which 2

show the remaining 77 inline SOVs used on the project have been reviewed.

One additional SOV was found to be oriented incorrectly.

1 The design documents which show the incorrect orientation of-- the two valve's have been corrected. The affected valves have been removed and reinstalled correctly in the field.

' It has been determined that the discrepancies noted were isolated cases, and no programmatic changes are necessary to preclude recurrence.

Corrective Action 1

FSAR Change Notice F6.7-1 was signed in December 1984 to indicate the correct installation position.of the valve.

Conclusion The incorrect installation of these valves would have been discovered 4

during preliminary testing. River Bend Preoperational Test Procedure No. PT-208 describes testing for the MS-PLCS. Note that in Section 7.3.6 of PT-208 (attached), proper closing of IE33*SOVF014 is verified.

1E33*SOVF014 is designed to close when the d/p between the steam line and the reactor is 8.5 1 3.0 psid. Installed incorrectly, IE33*SOVF014 would

not close with the PVLCS air supply (101 psig minimus) under the seat.

, The pressure in the main steam line would continue to increase, indica-ting a probler with the system. IE33*SOVF014 is the inboard bypass solenoid valve. 1E33*SOVF034 is the outboard bypass solenoid valve, which operates.and is tested in a similar manner.

C4/12210/555R/4YH w- -

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-9 Applicant ID No.: IE33*SOV14 Finding No. 2 If the working fluid (air) provides opening force; what is the minimum air pressure required to open the valves?

Response

The process fluid (air) pressure can drop to zero, and the valve will still operate. The valve operation is described in the vendor instruc-tion manual SWEC File No. 3247.501-240-004C. (See attached excerpts for additional details.)

Corrective Action None required.

Conclusion The valve installed with the flow over the seat will operate, as de-signed, at any pressure from 0 to 200 psig (system design pressure).

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C4/12210/555S/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-9 Applicant ID No.: 1E33*SOV14 Finding No. 3 Are the forces delivered by the spring capable of closing the valve against the loads of the working fluid?

Response

Yes, the valve is designed to close against a maximum AP. The maximum AP for IE33*S0VF014 is 200 psig (reference Specification. No. 247.501, page 1-48, lines 42.32 to 42.37; Drawing No. 0247.501-240-010F). The design pressure for line 1-MSI-002-60-2-(A-), which contains this solenoid valve, is 200 psig.

Corrective Action None required.

Conclusion This valve installed with flow over the seat will operate as designed.

C4/12210/555P/4YH 1

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE'3.10.2.1

- PVORT ID No.: BOP-9 Applicant ID No.: 1E33*SOV14 Findina No. 4 What assurance is there that the delivered air quality is in accordance with the manufacturer's requirements?

Response

The process conditions were provided in Specification No. 247.501. The manufacturer has not identified any special process media quality requirements. The system air supply is free of particulates. Air from the auxiliary building atmosphere is drawn into the water seal ring air compressor through an inlet filter-silencer. Seal water is initially fed to the compressor through a strainer and subsequently recirculated. The compressed gas-water six is fed to a separator where the water (and any solid particles) drop to the bottom, and the compressed gas rises. The rising- compressed gas is fed through an air filter to the LSV air accumulator.

Corrective Action None required.

4 Conclusion This valve will operate as , designed with air supplied by the PVLCS compressors.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO.-50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-9 Applicant ID No.: IE33*SOV14 Finding No. 5 List tests performed by GSU to date or to be performed in the future.

Response

No tests have been performed to date. System functional requirements will be verified by preoperational test procedure PT-208 including:

1. Pressurization of the MSIV from 0-35 psig within 5 minutes
2. Flow meter N006/N026 alarm and isolation at 12 scfm 10.5 flow -

and recorder alarm at 6 scfm 10.5

3. Functional isolation value test
4. Containment and main steam pressure interlocks set at 35 psig; minimum air supply interlock set at 50 psig
5. Functicaal drain valve test
6. Functional bypass valve test Corrective Action f .

Not applicable to this item.

Conclusion Not applicable to this item.

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C4/12210/555BB/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-9 Applicant ID No.: IE33*SOV14 Finding No. 6 How will GSU track manufacturer's recommendations regarding maintain-ability of components subject to aging.

Response

GSU's response to SSER Section 3.10.1.4, Finding No. 3 addresses how GSU's maintenance and surveillance program will track and identify com-ponents subject to aging.

Corrective Action Nene required.

Conclusion GSU has committed to have its maintenance and surveillance program, re-garding limited-life components, in effect before fuel load.

C4/12210/555AR/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT I DOCKET No. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: . BOP-11 Applicant ID No.: 1HVC*MOVIB Findina Actuator is serialized (260880). Adapter plate is also serialized (260953). PVORT form picked up the adapter serial number in place of the actuator number. Clarification required.

Response

The PVORT ' form provided to the NRC at the time of the audit listed the valve S/N 10837-4B (1981) and the actuator gear attachnient S/N 260953.

The actuator and actuator motor are also serialized. This data was not included on the original PVORT form. The serial numbers are as follows for the valve and appurtenances:

1. Valve S/N 10837-4B
2. Actuator S/N 260880
3. Actuator gear attachment S/N 260953
4. Actuator motor S/N 719390-PF Corrective Action The PVORT form has been revised to include the above serial numbers (attached).

Conclusion .

The PVORT forms were prepared at the request of the NRC for its use to aid in the review of the specific equipment included within the audit

. scope. Retrieval of all qualification documents for this equipment is controlled via the. equipment mark number, not component serial numbers.

GSU believes that the serial numbers which were missing from the PVORT fom have no impact on the qualification of the equipment in question.

C4/12210/5551/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-12 Applicant ID No.: 1E12*PC003 Finding No. 1 The specification identifies the operating fluid as demineralized water on the data sheet, while the pump retually takes suction from the sup-pression pool. What effect does this have on operability, performance, and life of wear rings, bearings, seals, impellers, etc?

Response

The suppression pool wster quality is maintained to the specification listed below (reference GE Document No. 22A2747, MPL A62-4130). Since there is no significant difference between this and demineralized water, there will be no deviation from the design performance or life of the pump or pump components.

Conductivity 10 unho at 25*C Chloride (as C1) 0.5 ppm Ph 5.3 to 8.6 at 25*C Total insolubles 5 ppm Corrective Action None required.

Conclusion ,

Since suppression pool water chemistry is essentially the same as demineralized water, there is no degradation in pump operability or maintainability.

C4/12210/555Y/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-12 Applicant ID No.: IE12*PC003 Findina No. 2 At reduced voltages, what is the capability of the p ap/ motor, and does

.it-meet the requirements of the system?

~' Response Based on Gould/ Westinghouse correspondence (reference letter dated i November 28,19a4, and TWX dated January 8,1985), the RHR fill pump is capable of achieving required system conditions of flow and pressure at a 70 percent voltage.

Corrective Action None required.

Conclusion Pump IE12*PC003 meets the requirements of Purchase Specification No. 237.160.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 l

SSER TABLE 3.10.2.1

- PVORT ID No.: B0P-13 Application ID No.: ISWP*P2A Finding-No. 1 Documentation provided for the staff review included factory performance test results, vibration test results from a coupled run, preliminary alignment data, and various. test procedures. r The performance data agreed with specification requirements; however, the staff ,

notes that the vibration data presented used peak velocity in inches per second '

and the General Machinery Vibration Severity (GMVS) Chart for acceptability as opposed to the pump specification requirement that peak to peak vibration amplitudes are not to exceed the limits shown on Figure 66 of the Hydraulic Institute (HI) Standard. The staff's concern is that this inconsistency in the use of vibration parameters can lead to errors when comparisons are made with baseline data; also, the acceptance criteria used by GSU in conjunction with-the GMVS Chart appear to be less conservative than the limits found on Figure 66 of -the HI Standard.

Response

The vibration acceptance criteria are included in Preoperability Test Procedure No. PT-256 and SWEC Document Nos. G232.920-257-001B, 002C, 0038, and 004C.

These documents were presented to the NRC reviewer during the audit.

4 The NRC's consultant followed this response with the further request that GSU confirm that acceptance critt'f a developed from the GMVS Chart do not exceed

- the criteria of Figure 66 in the HI Standard as requested in the purchase specification for the pump.

The following reviews were completed to address this followup request.

The vibration acceptance criterion is identified in Preoperational/ Acceptance -

a Test Procedure No. PT-256 as 0.314 in./sec. This criterion is verified by Generic Test Procedure No.1-G-ME-07, . Vibration Testing of Rotating Equipment, P Enclosure 11.2, which provides a GMVS Chart extracted from the IRD Mechanalysis Instruction Manual for the vibration monitoring equipment being used. The

Generic Test Procedure, in quoting from the vibration monitoring equipment
instructions, in Section 7, specifies that when recording vibratfor amplitude, displacement should be recorded for frequencies equal to or less than 600 cycles-per-minute (CPM), velocity should be recorded for frequencies greater 1 e n ..,n .,,,,-,ns -,,,---ne - ,- - - , - - - , . - - ----------a,L-m-- ~

than 600 CPM but equal to or less than 60,000 CPM and acceleration for frequencies above 60,000 CPM. For the rated operating speed of this pump, which is 1,200 CPM, it is therefore entirely consistent with generally accepted practice to measure the vibration amplitude in terms of inches per second, and the use of this vibration parameter should not lead to errors as stated in one concern noted by the NRC. The reason vibration velocities are the preferred measurement in this frequency range is that the corresponding peak-to-peak displacement amplitudes become quite small and are difficult to measure with the desired degree of precision.

The actual vibration test data, as documented in Enclosure 11.1 of 1-G-ME-07, has a maximum vibration of 0.10 in./see for the coupled run and 0.045 in./sec for the uncoupled run. Therefore, the actual vibration values are well within acceptable limits, when compared with the criterion of 0.314 in./sec given above.

For harmonic excitation, it is well known that the following simple relationship exists between the vibration velocity and the peak-to-peak displacement amplitude.

D = 19,100 V/ CPM where D is the peak-to-peak amplitude in mils, V is the velocity in inches per second, and CPM is the frequency of the vibration in cycles per minute.

Applying this relationship to the 0.10-in./sec velocity measured for the coupled run above, at the rated speed of the pump, a displacement of 1.59 mils peak-to-peak is computed. This compares with the acceptance criterion of 4.4 mils peak-to-peak given in Figure 66 of the HI Standard, which demonstrates clearly that based on this criterion the vibration values are also well within acceptable limits.

An additional review was completed to address the NRC's concern that acceptance criteria used by GSU in conjunction with the GMVS Chart appear to be less conservative than the limits found on Figure 66 of the HI Standard. These acceptance criteria are compared in the following table for a range of frequencies of vibration.

Peak-To-Peak Maximum Allowable Vibration Frequency of Amplitude, mils Vibration Figure 66 - Hydraulic General Machinery CPM Institute Standard Vibration Severity Chart 800 5.3 7.1 1000 4.8 5.8 1200 4.4 5.0*

1600 3.8 3.7 2000 3.4 2.9 3000 2.5 2.0 -

  • Corresponds to the 0.314-in./sec velocity criterion for this pump.

It can be seen by inspecting this table that in the lower frequency region the HI Standard is more conservative, and for frequencies above 1,600 CPM the GMVS Chart is more conservative. At the rated operating speed of this pump (which is 1,200 CPM), the two are within 13.6-percent agreement of each other, which sould be acceptable for practical engineering applications. For this pump, the HI Standard Figure 66 is more conservative, as the NRC reviewer correctly pointed out. However, it also should be noted that the HI Standard,

13th Edition, p 106, states in connection with Figure 66 that the curve should be used as a general guide, with recommendations that vibrations in excess of the curve may require investigation and correction. Often, more important than the actual vibration itself are the changes of vibration over a period of time.

Vibrations in excess of the curves may often be tolerated if they show no increase over considerable periods of time and if there is no other indication of damage, such as increase in bearing clearances.

As part of the RBS preventive maintenance and surveillance program, all large rotating equipment of the type under discussion is routinely inspected. RBS vibrating monitoring program, PEP-0003, defines the measurement methods, computerized data retention and analysis, and frequency of recording data on the equipment. The frequency of monitoring motors is established at every 28 days, and pumps are monitored quartely. For this pump, an alarm level is set at 0.2-in./sec vibration velocity magnitude. This is considerably below the criteria in either Figure 66, which is 0.276 in./sec (derived from the 4.4 mils displacement and the equation given above), or the GMVS Chart which is 0.314 in./sec.

An alarm level is a preselected vibration value placed into the vibration data bank for each equipment that causes an alert to be signaled to the operator indicating possible vibration problems.

Corrective Action None required.

Conclusion From the discussion, it is concluded that inconsistencies in the vibration parameters, peak-to-peak displacement, or vibration velocity, will not arise since a simple relationship exists to equate the two.

Also, a study relative to the NRC's concern that acceptance criteria used by GSU in conjunction with the GMVS Chart appear to be less conservative than the limits found on Figure 66 of the HI Standard showed the two criteria are within 13.6 percent of agreement with each other which is considered acceptable for practical engineering applications. It should be noted in connection with Figure 66, the HI Standard states that this is a general criteria only, and higher levels of vibration may be acceptable. In addition, since the alarm setting for the level of vibration in this pump is established well below either of the two criteria, it is concluded that the NRC's concern is resolved.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 ~

DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-13 Applicant ID No.: ISWP*P2A

, Finding No. 2 Coupling runout value (driven member) is ine'nsistent o with alignment requirement.

Response

The coupling runout value is the difference between the minimum outside diameter and the maximum outside diameter of the coupling. This value is witbin manufacturer's tolerances.

The vendor's instructions state that the pump and motor shafts are to be aligned axially within 0.002 in. The shaft alignment record shows that the measurement taken was 0.001 in, at 180' and 270' and 0.000 in.,at 0*

and 90'. Also, the faces of the motor half coupling and the adjustable spacer must be parallel within 0.002 in. The shaft alignment record shows that the angular alignment value was 0.000 in. Therefore, the alignment requirements of the vendor have been met.

Corrective Action Not applicable to this finding.

Conclusion All coupling alignment readings were found to be within manufacturer's tolerances.

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s b, RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-13

-Applicant ID No.: ISWP*P2A Finding No. 3 Pump weight incorrect on PVORT sheets.

Response

Correct pump weights are as follows:

Pump Assembly (dry): 26,500 lb (Add 2, Rev. 1, Spec)

Pump Assembly (filled with water): 36,670 lb (Add 2, Rev. 1, Spac)

Motor: 5,500 lb (Motor Analysis)

These weights were considered in the seismic analysis of the pump and motor, contained in the following references:

SWEC File No. 6232.920-257-005D - Motor SWEC File No. 4232.920-257-001B/1C - Pump Assembly Copies of the weight references are attached.

Corrective Action TLe PVORT form has been revised to show the correct values (attached).

Conclusion .

This finding was the result of an errer made during the preparation of the PVORT sheets, which were prepared only to facilitate NRC review during the audit. Since the correct equipment weights were considered in assessing seismic qualification results, this finding has no significance in terms of the overall adequacy and effectiveness of the program.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-13 Applicant ID No.: ISWP*P2A Finding No. 4 Final qualification subject to compliance with endurance testing recom-mended in IE Bulletin 83-05.

Response

GSU's position on performance / endurance and hydrostatic pressure testing.

was provided in a letter from Dr. J. G. Weigand to Mr. J. T. Collings dated August 16, 1984. This letter provided information and commitments which satisfied the concerns of IE Bulletin 83-05.

Corrective Action The ' comitments made in this letter are documented as Commitments 25 through 35 in GSU's Internal Comunitment Tracking System and will be tracked to completion by the GSU Licensing Group.

Conclusion The question concerns an IE Bulletin and P controlled by GSU's Internal j

Commitment Tracking Program as mentioned above. Therefore, IE Bulletin concerns are addressed via a GSU program and are not considered indica-tive of any programmatic problems with the SQRT/PVORT EQ Program.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-SURPRISE Applicant ID No.: IE12*MOVF021 Finding No. 1 Have stem leakoff requirements been met?

Response

The subject valve was provided with a . stem leakoff connection in accordance with the valve technical data sheet included in SWEC Specifi-cation No. 228.212. A short length of 1/2 in. , schedule 80 pipe con-nected to the valve body is provided, as shown on the Volan Company valve drawing (SWEC File No. 0228.212.047-011E). This connection is not used on River Bend and, therefore, is not piped up to a permanent drain point.

The leakoff is to be plugged in accordance with applicable requirements provided in Piping Erection Specification No. 226.160 and on the instal-lation drawing. A photograph of the stem leakoff connection was provided to the NRC inspector during the audit.

Corrective Action None required.

Conclusion

! Stem leakoff provisions for this valve are consistent with the engineer-

'ing requirements documents. . SWEC design procedures require piping up valve stem leakoffs for high pressure and/or high-temperature applica-tions only and this valve does not fall in this category.

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  • r RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-SURPRISE Applicant ID No.: 1E12*MOVF021 Finding No. 2 N&D No. 6189 states that motor stator housing was welded to motor flange.

Have possible effects of welding on valve flange and valve shaft assembly been considered?

Response

During the walkdown of the equipment, the NRC reviewer, R. Hodor, ques-tioned the fact that the actuator motor was missing and asked the reason for the ' reject Tag No. Y400361-1, which was attached to the valve actua-tor. In response to these questions, the Nonconformance and Disposition Report (N&D) No. 6189 was made available to the NRC reviewer which ex-plained the reason for the missing motor and the reject tag. As a result of the questions asked during the audit, SWEC conducted a review of the circumstances which caused the N&D to be initiated. The results of this review indicate that:

1. The motor and housing were properly bolted to the stator housing and then tack welded.
2. - The nipple where the electrical conduit enters the housing was properly threaded into position and then tack welded.
3. The motor housing . vent was threaded into position then tack welded.

Based upon the above, it appears that a conservative disposition was provided for the N&D (i.e., remove / replace motor).

After consulting with SWEC's Material Engineering, it was concluded that the amount of heat -generated from tack welding is negligible and as such will not cause any warping of the flanges or cause any significant residual stresses that would affect the operation or qualification of the motor operator and/or the valve shaft assembly.

4 Corrective Action The motor has been replaced, and the valve assembly was successfully tested on January 26, 1985.

C4/12210/555C/4YH 1 ,

Conclusion The tack welding performed on the motor stator housing had no effect on the valve flange and -valve shaft assembly, as demonstrated by the successful completion of the valve assembly testing.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: BOP-SURPRISE Applicant ID No.: 1E12*MOVF021 Finding No. 3 The dates of issue on qualified documents are very recent (i.e., ST-7003, Operability Test Procedure, is dated November 2,1984, which was the exit meeting date. Completeness and approval are required.

Response

Operability Test Procedure No. ST-7003 was approved on November 2,1981.

The PVORT form for the subject equipment erroneously lists this date as November 2, 1984. However, the Operability Qualification Test Report (SWEC File No. 6228.212-047-105A) was approved on November 1, 1984. With the approval of this report, all qualification documents have been received by SWEC, reviewed, and approved.

GSU was notified, immediately prior to the audit, that the subject equipment would be included in' the audit. The Equipment Qualification Master List, a copy of which was provided to the NRC prior to the audit, indicated that the qualification process for the subject equipment was not complete (status shown was " test complete but test report not approved.") Since the Operability Qualification Test Report had been received by SWEC, and in order to provide complete qualification documentation for the NRC reviewer, SWEC proceeded to complete the review / approval of this report to support the audit. The report was approved on . November 1, 1984, I day prior to the audit exit meeting.

Corrective Action The PVORT form for the subject equipment has been revised to correct the

approval date of -the Operability Test Procedure. Also, the Operability Qualification Report has been added to the list of documents on the PVORT form (see attachment).

Conclusion The incorrect date shown on the PVORT form was a data transcription error which occurred when the form was prepared.

C4/12210/555B/4YH

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SSER RESPONSES

,, RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: NSSS-5 Applicant ID No.: E22-F015 .

Findina 4

The operability of the valve was established using analysis only. A test program is presently being performed, . and a similar analysis with a similar valve which was tested will be submitted as demonstration of

. operability and qualification.

Response

Static deflection testing has been completed for representative samples of- the full family of HPCS valve sizes including the smallest at 4 in.

and the largest at 24 in. All valves are dynamically qualified for the i- RBS _ application. The results will be documented in the qualification report prior to fuel load.

, The l NRC's consultants followed this response with the further comment that the response by GSU does not -indicate that a similarity analysis considering fluid dynamic and seismic effects under normal, accident, and post-accident conditions is in process or completed. Resolution of the concerns will require documented results of the static deflection testing and similarity analysis, i

Static deflection testing was_ performed on the full family of HPCS valve sizes, as stated above. The operability of the 20-in. valve- under

. discussion can best be demonstrated from the test results of a similar i

24-in. valve. This valve is outside the range of valves installed at the River Bend Station, but has parameters which most closely match the cur-rent valve. The 24-in. valve tested and the 20-in. valve being qualified have the same pressure ratings. Operability of the 24-in. valve was demonstrated by _ cycling open and closed under the full design pressure of 100 psig, or 90 psig across the gate for the closed valve, which cor-responds to the RBS design pressure. Simultaneously, the motor operator

- was deflectad by the application of a force corresponding to 8 g, which compares with the 3.5 g faulted loading requirement for any direction for i

RBS. Extension of these results qualifies the E22-F015 candidate valve by similarity, which is in addition to previous analyses documenting the stresses and stern deflections for the RBS loading. The above is documented in DRF No. 126-E22-LDO-1, River Bend High Pressure Core Spray E22-F015 New I,oads Evaluation, Rev.1, March 25,1985.

i C4/12210/555AT/4YH 1

In addition, a 12-in. gate valve parent design was dynamically and seismically tested with considerable margins (reference VPF No. 5485-95-1), in accordance with GE Specification No. 23A1361, to demonstrate operability due to dynamic flow-induced vibration, SRV aging, and upset, faulted, and chugging loads. Operability results of the parent valve may be extended to the E22-F015 candidate valve due to design similarity.

Corrective Action None required.

Conclusion The application of static deflection testing of a similar valve design cycled open and closed under the same design pressure conditions and with a simultaneous loading with over 100 percent margin adequately demon-strates the operability of the valve under discussion.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.2.1

' PVORT ID No.: NSSS-7 Applicant ID No.: E12-C002C 4

Finding No. 1 How is pump performance (curves, vibration levels, bearing temperature, etc) established without the use .of manufacturer's data / acceptance criteria?

Response

Evaluation of the RHR pump and motor performance is directly dependent on vendor data. Some examples of documents / procedures which utilize spec-ification and vendor data are listed below.

1. FSAR, Chapter 14, Initial Test Program -

14.2.12.1.5(4.b.)

" Pump head flow characteristics and NPSH are as specified by the GE preoperational test specification for the following modes of operation: LPCI, shutdown cooling, and suppression pool cooling."

2. 22A5296 AG, GE Preoperational Test Specification, Appendix B, GE-5 Residual Heat Removal -Prescribes the minimum testing requirements necessary to verify residual heat removal (RHR) system capabilities to meet design requirements. Under Section B5.1, Supporting Documents, a list of vendcr documents is given. Among them are:

~

RHR Pump, Vendor's Instruction Manual RHR Pump, Certified Performance Curves ,

3. 1-G-ME-04, Generic Test Procedure, Preliminary Testing of '

Pumps.

2.0 References 2.1 " Applicable Vendor Technical Manuals" i 3.0 Prerequisites 3.1 " Verify that cold alignment data complies with the 1 manufacturer's specification. Allowance for thermal ex-pansion should be made as required by vendor technical manual or system specification."

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i. 4 3.4 "The test engineer shall review the vendor technical manual and specification data for the panel and motor prior to starting the test. This review should include all specific operating parameter limits, specific accep-tance criteria, and instructions relative to startup and initial pump operation."

3.5 "If required, ensure that a vendor representative is present for the initial run of the pump."

5.0 Limitations and Precautions 5.2 "Do not exceed the manufacturer's operating limits of number of successive motor starts."

5.5 " Secure the panel if bearing temperature, lube oil pressure, or seal leakage specified on the pump design data sheet or instruction manual are exceeded."

7.0 Procedure 7.1 Centrifugal Pumps ,

7.1.15 " Plot the above data on manufacturer's curve and attach to Enclosure 11.1. Indicate on the curve any head or flow limits given in the specification."

10.0 Acceptance Criteria 10.1 " Pump performance shall closely approximate the manufacturer's shop curve (7.1.15)."

4. 1-G-ME-07, Generic Test Procedure, Vibration Testing of '

Rotating Equipment 3.0 Prerequisites 3.7 "The Test Engineer shall be aware of any specific vibration limits, test points, or. test methods that are called out by the equipment specification or vendor manual."

10.0 Acceptance Criteria 10.1 " Data shown on Enclosure 11.1 shall be compared to limits supplied by the manufacturer, found in either the contract - specification or found in the operating manual.

Where no information is given, data shall be compared to the General . Machinery Vibration Severity Chart (Enclosure 11.2)."

Actual test results are available showing the design limits and the RHR pump, certified performance curves which were extracted from vendor and specification data. Three examples of actual test results are given as C4/12210/555BC/4YH 2

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evidence ' that vendor / specification data are utilized and documented on the following data sheets:

1. 1-G-ME-04, BIP-1-BX-RHS.000, CSU System-204, Date 04/04/84
2. 1-G-ME-07, BIP-1-RHS.000, CSU System-204, Date 05/24/84
3. 1-G-ME-07, BIP-1-RHS.000, GSU System-204, Date 08/27/84 Corrective Action None Conclusion Usage of Vendor / Specification data pervades the GSU preoperational start-up and test program, and no problem is evident in this area.

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: NSSS-7 Applicant ID No.: -E12-C002 Finding No. 2 Discharge pressure transmitter has a reject tag and as-built acceptance tag. Clarify the difference and the reason for the reject tag and the action taken.

Response

The reject tag was attached to the transmitter because differential stud projections indicated that studs may not have been fully engaged (dirt also present). Inspection Report (IR) No. M4000946 documents this concern. The concern was resolved by reworking the studs in accordance with Construction Work Request No. 4543.

As-built tags are applied to components to identify that as-built dimen-sional measurements and orientations have been taken for the component.

Reject tags are applied by FQC when any component deviation is-identified on an unsatisfactory IR or Nonconformance and Disposition (N&D) report.

Both tags may exist simultaneously on a component.

Corrective Action I l Not applicable to this item.

!' Conclusion

-Not applicable to this item. 1 l'

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: NSSS-7 Applicaat ID No.: E12-C002 Findina No. 3 Serial number on documentation and long form disagree.

Response

The serial number on the long form was for a motor that was identified for RBS Unit 2. The correct serial numbers for RBS Unit I are CNJ 316027, 316028, and 316029. These serial ~ numbers agree with the documentation.

Corrective Action Not applicable to this item.

Conclusion Not applicable to this item.

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C4/12210/555AV/4YH

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RBS-EQUIPMENT QUALIFICATION PROGRAM SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET NO. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: NSSS-7 Applicant ID No.: E12-C002 Finding No. 4 Clarify the differences between GE Specification Nos. 21A3504, Rev. I and 21A3504BV, Rev. 0 (e.g., removal of IEEE Standards - is this component built to IEEE, if not justified why).

Response

Specification No. 21A3504, Rev. 1 is the base specification which forms a part of the plant-unique data sheet Specification No. 21A3504BV, Rev. O.

Specification No. 21A3504BV, paragraph 2.2.1, states that if there are conflicts between the two specifications, the plant-unique document, Specification No. 21A35041BV, Rev. O, shall govern. Based on this, IEEE standards were not removed from the order since they were required in Specification No. 21A3504, Rev. I and were not retracted or superseded by a statement to that affect 'in Specification No. 21A3504BV, Rev. O. In this area, there were no conflicts between the two specifications; there-fore, IEEE standards were required. The motors were built to the IEEE standards identified.

Corrective Action Not applicable to this item.

i t Conclusion .

Not applicable to this item.

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RBS-EQUIPMENT QUALIFICATION PROGRM1 SSER RESPONSES RIVER BEND STATION - UNIT 1 DOCKET No. 50-458 SSER TABLE 3.10.2.1 PVORT ID No.: NSSS-7 Applicant ID No.: E12-C002 Findina No. 5 j

Clarify how GSU will or has identified parts censitive to aging mechan-isms and how they will be tracked.

Response

GSU's response to SSER Section 3.10.1.4, Item No. 3 addresses how GSU will identify will and track parts sensitive to aging mechanisms and how they be tracked.

Corrective Action Not applicable to this item.

Conclusion Not applicable to this item.

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