ML20237G763

Summary of 870819 & 20 Meetings W/Util at Facility Re Status of Technical Issues Requiring Resolution Prior to Restart. List of Attendees,Agenda & Handouts Encl

ML20237G763
Person / Time
Site:	Sequoyah
Issue date:	08/26/1987
From:	Mckenna E NRC OFFICE OF SPECIAL PROJECTS
To:	NRC OFFICE OF SPECIAL PROJECTS
References
NUDOCS 8709020400
Download: ML20237G763 (81)

Text

_ _ - _ _ - _ _ _ - _ - _ _ _ _ _ _.

[

UNITED STATES

[

NUCLGAR REGULATORY COMMISSION E

5 WASHINGTON, D. C. 20555 y*****j August 26, 1987

' Docket No.

50-328 FACILITY:

Sequoyah Nuclear Plant, Unit 2 LICENSEE:

TennesseeValleyAuthority(TVA)

SUBJECT:

MEETING

SUMMARY

-AUGUST 19 AND 20, 1987

)

On August 19 and 20, 1987, members of the NRC staff met with TVA at the Sequoyah site to discuss the status of technical issues requiring resolution for Sequoyah Unit 2 restart; A list of attendees is provided in Enclosure 1.

The handouts and agenda used during the meeting are provided in Enclosure 2.

TVA discussed its schedule for heatup of Unit 2.. The final check of valve j

alignments is scheduled to begin September 7, 1987, with planned entry into Mode 4 (hot shutdown) being September 28, 1987. TVA's goal is to coniplete as many issues as possible prior to September 7,1987 to allow a three-week

" quiet period" for operations to demonstrate their state of readiness to begin plant restart.

.The staff intends to conduct similar status meetings with TVA on a inonthly basis for the foreseeable future.

A Eileen McKenna, S nior P nager TVA Projects Division Office of Special Projects

Enclosures:

1.

List of Attendees 2.

Agenda and Handouts cc w/ enclosures:

See next page

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I-August 26c 1987 Docket No.

50-328 1

s FACILITY:

Sequoyah Nuclear Plant, Unit 2 LICENSEE:

Tennessee Valley Authority (TVA)

SUBJECT:

MEETING

SUMMARY

-AUGUST 19 AND 20, 1987 On August 19 and 20, 1987, members of the NRC staff met with TVA at the Sequoyah a

I site to discuss the status of technical issues requiring resolution for Sequoyah Unit 2 restart. A list of attendees is provided in Enclosure 1.

The handouts and agenda used during the meeting are provided in Enclosure 2.

TVA discussed its schedule for heatup of Unit 2.

The final check of valve alignments is scheduled to begin September 7, 1987, with planned entry into Mode 4 (hot shutdown) being September 28, 1987. TVA's goal is to complete as many issues as pussible prior to September 7, 1987 to allow a three-week

" quiet period" for operations to demonstrate their state of readiness to begin plant restart.

Tha staff intends to conduct similar status meetings with TVA on a monthly basis for the foreseeable future.

Original signed by:

Eileen McKenna, Senior Project Manager I

TVA Projects D1 vision j

Office of Special Projects 1

/

Enclosures:

1.

List of Attendees l

2.

Agenda and Handouts I

cc w/ enclosures:

See next page

)

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TVA:0SP/LA TV :d M

TVA:AD/P CJamerso 1 EMcKenna:pw JZwolinski 6/ Q87 B J)6/87 Q /)y87 7

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Tennessee Valley Authority Sequoyah Nuclear Plant i

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Genera 1' Counsel Regional Administrator, Region II Tennessee Valley-Authority U.S. Nuclear Regulatory Comission 400 West Sumit Hill Drive 101 Marietta Street, N.W.

E11 B33 Atlanta, Georgia 30323 Knoxville, Tennessee 37902 Pesident Inspector /Sequoyah NP Mr. R. L. Gridley c/o U.S. Nuclear Regulatory Comission Tennessee Valley Authority 2600 Igou Ferry Road SN 157B Lookout Place Soddy Daisy, Tennessee 37379 Chattanooga, Tennessee 37402-2801 Mr. Richard King Mr. H. L. Abercrombie e/o U.S. GAO Tennessee Valley Authority 1111 North Shore Drive Sequoyah Nuclear Plant Suite 225, Box 194 P.O. Box 2000 Knoxville, Tennessee 37919 Soddy Daisy, Tennessee. 37379 Tennessee Department of Mr. M. R. Harding Public Health Tennessee Valley Authority ATTN: Director, Bureau of Sequoyah Nuclear Plant Environmental Health Services P.O. Box 2000 Cordell Hull Building Soddy Daity, Tennessee 37379 Nashville, Tennessee 37219 Mr. D. L. Williams Mr. Michael H. Mobley,. Director Tennessee Valley Authority Division of Radiological Health 400 West Sumit Hill Drive T.E.R.R.A. Building W10 B85 150 9th Avenue North Knoxville, Tennessee 37902 Nashville, Tennessee 37203 County Judge Mr. S. A. White Hamilton County Courthouse Manager of Nuclear Power

' Chattanooga, Tennessee 37402 Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

1 i

I ENCLOSURE 1 NRC/TVA MEETING August 19, 1987 Name Affiliation Phone #

i Bob P~ierson OSP/TVA/PSB 301-492-9039 David Kunsemiller DNSL/ SON 615-870-7619 Jerry *Cochran LIC/ SON 615-870-7620 Eileen McKenna OSP/TVA Projects 301-492-7745' John A. Zwolinski OSP/TVA Projects 301-492-9696 Mark Burzynski SON /LIC 615-870-6172 David P. Ormsby SON /CLS 615-870-6644 W. K. Poertner NRC Inspector 615-870-6124 G. T. Hubbard OSP/TVA Projects 615-492-4825 Janet Kelly OSP/TVA Projects.

615-492-4835 i

Mike Harding TVA/ SON SITE LIC MGR 615-870-6422 y

-Jim'Clifford NRC/OSP 301-492-9045 l

B.'C. Morris BFNP/LIC 205-724-3604 205-729-5015

.T. G. Chapman' T'IA/BFEP R. D. Briggs TVA/DNE 615-874-5317 l Charles McWherter TVA/ Materials 615-870-7807 Charles H. Whittemore TVA/LIC (SON) 615-870-7210

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o NRC/TVA MEETING August 20, 1987 Name Affiliation Eileen McKenna NRC/05P Janet Kelly NRC/OSP C. R. Brimer TVA-DNE David G. Renfro TVA-DNE-SOEP George Hubbard NRC/0SP Jim Clifford HRC/OSP T. G. Chapman TVA/BFEP B. C. Morris.

BFN-Licensing T. A. Ippolito TVA-Licensing David A. Pullen TVA-BEN John A. Zwolinski NRC/OSP/TVA Gary G. Zech NRC/OSP/TVA Jack Donohew NRC/OSP/TVA Dave Kunsemiller TVA/DNSL M. A. Bowidowicz Sargent & Lundy BFN l

Jerry Cochran TVA/Lic John LaPoint TVA Morris Branch NRC Kent Brown TVA-EEB Knoxville John Hosmer DNE-SON-PE Bruce Schofield TVA/LIC SON Wayne'A. Massie TVA/ SON LIC Frank A. Koontz Jr.

TVA/DNE/ NEB' Robert E. Roemer Stone & Webster R. H. Buchholz Site Representative l

Jim Hutson TVA/DNE/EEB David P. Ormsby TVA/ SON /CLS Mike' Harding SON Licensing Beth Hall SON Licensing Paul Harmon NRC j

Tom Knight TVA

)

Ken Jones TVA

~

ENCLOSURE 2 AGENDA SEQUOYAH NUCLEAR PLANT TVA/NRC MEETING ON AUGUST 19-20, 1987 (Page 1)

Augu;t 19, 1987 PURPOSE OF MEETING Provide overall status of issues needing resolution by heatup and criticality.

Location:

plant conference room RESPONSIBLE ORGANIZATION / PERSON LICENSING TIME SUBJECT PRESENTATION REPRESENTATIVE 1:00 p.m.

1.' Technical Specifications M. Burzynski R. Headors 1:30 p.m.

2.

Auxiliary Feedwater Pump M. Burrynski M. Burzynski 2:'00 p.m.

3.

SIMS (Safety Issues Management NRC System) 2:30 p.m.

4.

Procurement NRC M. Purcell R. Cook (Heat Code Traceability)

D. Briggs C. Whittemore (Ray Miller Bulletin)

C. McWherter C. Whittemore 3:00 p.m.

5.

Containment Coatings J. Hohmer M. Harding M. Cooper Renfro/Brimer NOTE:

Each item is scheduled for approximately 30 minutes except (*) items scheduled for a total of 15 minutes and calculations program for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Please plan your arrival at'least 30 minutes in advance of estimated schedule.

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AGENDA SEQUOYAH NUCLEAR PLANT TVA/NRC MEETING ON AUGUST 19-20, 1987 (Page 2)

August 20. 1987 PURPOSE OF MEETING Provide overall status of issues needing resolution by heatup and criticality.

Location:

plant conference room RESPONSIBLE ORGANIZATION / PERSON LICENSING TIME SUBJECT PRESENTATION REPRESENTATIVE 8:30 a.m.

17 Heatup Schedule J. LaPoint M. Burzynski 9:00 a.m.

2.

Restart Criteria versus Licensing M. Burzynski technical specification during (M. Harding)

(M. Harding) mode 4 9:30 a.m.

3.

Trends in Operational Areas NRC

' maintenance /MR's

' modifications /ECNs

'CAQRs

~

' Commitments

~

10:00 a.m.*

4. Cable Testing K. Brown B. Kimsey

)

M. Burzynski 10:15 a.m.*

5.

Fuse Replacement J. Hutson B. Schofield j

10:30 a.m.

6.

Calculations Program J. Hosmer/F. Koontz B. Hall 10:30 a.m.

7.

Unverified Assumptions J. Hosmer/F. Koontz H. Massie 10:30 a.m.

8.

Calculation Regeneration J. Hosmer/R. Roemer B. Kimsey Program H. Burzynski 11:30 a.m.

9.

Hydrogen Analyzer J. Hosmer/J. Corry H. Massie Lunch Break 1:00 p.m.

10. Operational Readiness Site Director's Staff B. Schofield (T. Knight) 1:30 p.m.

11.

Restart Test Program Site Director's Staff B..Schofield (K. Jones) 2:00 p.m.

12.

Essertial Raw Cooling DNE/J. Hosmer M. Burzynski Water Pipe Replacement (C. Bowman)

• i NOTE:

Each item is scheduled for approximately 30~ minutes except (*) i tems scheduled for a total of 15 minutes and calcula_tions program for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />."

Please plan your arrival at least 30 minutes in advance of estimated i

schedule.

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03CHICAL SPEC"F::CA":0NS i

3emaining Submina..s

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Corrections to list of secondary containment bypass penetrations 2.

Addition of lower compartment cooler requirements for non-LOCA accidents 3.

Revieion to containment ventilation isolation response time 4.

Revision to auxiliary feedwater suction transfer setpoints 5.

Revision to fuel assembly weight for crane interlocks

-6.-

Miscellaneous typographical errors and incorrect references

S3QUOYAH "3CESICAL SPEC 3ICAT::0XS o

Reviews for Correctness and Completeness through programs Calculations Design Criteria DB & VP Technical Specification Tables Surveillance Instructions Administrative Normal Business 44 Technical Specification Changes identified o

4 Require NRC Approval for Restart 11 Considered Priority Submittals 29 Other Changes o

Current Status l

4 Changes Requiring Approval Submitted 34 Other Changes Submitted

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6 Changes in WA Approval Cycle (PORC/NSRB) o Actions Remaining for Restart

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- WA Submit Remaining Changes Prior to Mode 4 -

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1 PROCUREMENT TECHNICAL ISSUE:

Y PAST PROCUREMENT CONTROLS DID ASSURE QUALIFIED EQUIPMENT WAS INSTALLED IN PLANT CORRECTIVE ACTION:

REPLACEMENT ITEM PROGRAM (RIP)

UPGRADE PROCUREMENT PROCEDURES CORRECTION ACTION STATUS:

RIP NEAR COMPLETION SQA-45 AND AI-11 BEING UPGRADED AND IMPLEMENTED CRITICALUY ITEMS:

RIP COMPLETION RESOLUTION OF A-46 VERSUS IEEE-344 ISSUE CORRECTION OF REPORT 86-61L 87-40 FINDINGS COMPLETE REVISIONS OF SQA-45 AND AI-11 WITH SOME IMPLEMENTATION REVIEW 0F CEG AND IES DEDICATION PACKAGES CRITICAL CHARACTERISTICS

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RECEIPT INSPECTION REQUIREMENTS RECEIPT INSPECTION PROCEDURES

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RESPONSIBILITY FOR INSPECTION PERFORMANCE NRC REVIEW AND ACCEPTANCE OF CORRECTIVE ACTIONS

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1 ISSUE Does TVA have adequate assurance that apparently fraudulent Ray Miller, Inc., material has not been received and installed at E

Sequoyah Nuclear Plant?

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i CHRONOLOGY o

-In 1983-84 TVA investigated all material received directly.from Ray Miller, Inc., as well as' contacting numerous secondary suppliers.

TVA determined that no apparently fraudulent Ra', Miller, Inc,,

material had been received or installed at Sequoyah Nuclear Plant.

Nevertheless, all other material received from Ray Miller, Inc., was appropriately dispositioned.

o In Decembe.r, 1986, Employee Concerns Task Group (ECTG) j investigators concluded, during the investigation of a related concern,thatTVA[sresponsetoIEBulletin83-07wasinadequate.

Although the ECTG-investigators continued to be concerned, the Division of Nuclear Quality Assurance (DNQA) and ECTG senior management both independently reviewed and closed out the concerns.

o During an inspection conducted the week of July 20, l'87, the 9

Nuclear Regulatory Commission (NRC) concluded that sufficient documentation did not exist to show that TVA investigated all Potential secondary suppliers of Ray Miller material to TVA.

TVA has documentation of investigations of numerous secondary suppliers.

In addition, the NRC contacted all aecondarv l

' suppliers listed in the bulletin to ascertain it they had supplied apparently fraudulent Ray Miller waterial to licensees.

To date, TVA has agt been notified by the NRC or any secondary I

supplier of delivery of any apparently fraudulent Ray Miller

. material to Sequoyah.

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CONCLUSION In no. instance has apparently fraudulent Ray Miller, Inc.,

material been' identified as received, much less installed, at Sequoyah Nuclear Plant by DNQA, ECTG, NRC,.or anyone else.

We, therefore, conclude that the safety of Sequoyah Nuclear Plant has not been compromised because of the Ray Miller, Inc.,

fraudulent material incident.

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RESTART REQUIREMENT CRITERIA l

item The following criteria shall.be used in evaluating whether a partic l

must be resolved prior to startup..

4 The item identifies a specific deficiency which has significant-d for probabil',ty of leading.,tp the,inoperability of a system requir i

1.

hi l Specifications.

,startup or operation by the appropriate Tec n ca When evaluating potential operability problem l

NOTE:

shutdown thir$ ant, (11) maintain it in a safe shutdown

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condition..et.(iii) mitigate the consequenc 1

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.i The item identifies a programmatic deficiency which has a hig hich meets probability of_ causing or has caused a specific deficiency w j

2.

No. 1,above.'

8 To assist in the determination of required affirmative answer to any of the following questions. requi consideration of the item for restart based on T 1

Specification requirements.

Does the' item directly and adversely affe l

?

O a.

b Does the item indirectly and adversely a

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i ventilation?

W Does the item adversely affect 'pr4 mary containment. in Does the item adversely affect sarcondary con c.

d.

Does the item adversely affect control room habitability?

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Does the item. adversely affect systems used to process r f.

A waste?

Does the item adversely affect fire protection or fire load L

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a RESTART REQUIREMENT CRITERIA' Does the item adversely affect the ability of a system or component h.

to meet its safety function during a design basis event by inpacting the seismic Analysis, single fai' lure criteria, separation criteria, high energy line break assumptions, or equipment qualification?

Are the programs such as Radiological Health, Sec'urity, Radiological Emergency Preparedness, or Quality Assurance which are 4.

necessary for safe conduct of operation of the plant adversely I

affected?,

t If not corrected prior to restart, could it lead to an uncontrolled se or spread of radiohetive contamination beyond the regulated j.

relp!

arch The item identifies a specific deficiency that results in a failure to

-l comply'with NRC regulations and no variance has been approved by NRC 3.

NRC regulations means title 10 of the Code of Federal.

Regulations, NRC orders issued to TVA, License _ Conditions, and NOTE:

In order to

,l Technical Specifications applicable to Seouoyah.

comply with 10CFR50.59, any deviations from the Safety Analysis Report (SAR) that involve an Unreviewed Safety Question (USQ) must be resolved prior to restart.

4.

TVA has committed to NRC to complete the item prior to restart.

The item identifies a specific deficiency which has a significant probability of leading to a personal injury during plant operation.

5.

The item identifies a specific condition which has a, forced outage risk (probability X outage length) during the.next cycle ih excess of the--

6.

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critical path time to correct the condition prior to. restart.

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TOTAL SURFACE AREA OF NUCLEAR OUALIFIED COATINGS UPPER CONTAINMENT:

INORGANIC ZINC COATED STEEL (CZ-11) 27,000 FT2 EPOIY TOP-COATED STEEL (CZ-11, 305) 19,000 FT2 2

EPOIY CONCRETE (295, 305) 23,000 FT LOWER CONTAINMENT:

2 INORGANIC ZINC COATED STEEL (CZ-11) 52,000 FT 2

EPOIY TOP-COATED STEEL (CZ-11, 305) 27,000 FT

' -' '7 EPOIY COATED CONCRETE (295, 305) 25.000:FT2 I'

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LOCATION CONDITION (FT )

RESOLUTION

1) UPPER COMPARTMENT A) UNQUALIFIED 1391 DCDCIS SETTLES BEFORE' REACHING " CONE OF INFLUENCE" B) TOPCOAT SUBJECT TO APPROK DEBRIS SETTLES BEFORE

.j DELAMINATION 3050 REACHING " CONE OF INFLUENCE" a 1

2) LOWER COMPARTMENT.

A) UNQUALIFIED 1052 DEBRIS SETTLES BEFORE INSIDE CRANE WALL REACHING " CONE OF INFLUENCE" i

B) TOPCOAT SUBJECT TO 951 DEBRIS SETTLES BEFORE j;

DELAMINATION REACHING " CONE OF INFLUENCE" l

3) ICE CONDENSER A) UNQUALIFIED 173

. DEBRIS SETTLES BEFORE REACHING " CONE OF INFLUENCE" B) UNQUALIFIED 3

WESTINGHOUSE ANALYSIS

4) ACCUMULATOR ROOMS A) ENTRAINED WATER 40 MIL WIME MESH COVERS 3 AND 4 FROM AIR RETURN DRAIN

~ FANS s

5) CONE OF INFLUENCE UNQUALIFIED 53 WESTINGHOUSE ANALYSIS (OVER SUMP)

6) SEE LOCATIONS ON A) UNQUALIFIED 5537 REWORKED DURING THIS OUTAGE ELEVATION B) DELAMINATING 5599 REWORKED DURING THIS OUTAGE-0037C

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SON UNIT 7 OPERATIONAL READINESS EVALUATION RESTART ISSUE:

PROVIDE A SYSTEMATIC ASSESSMENT TO ASSURE THAT SON UNIT 2 IS READY TO RESTART AND PROVIDE FEEDBACK TO THE SITE DIRECTOR.

OPERATIONAL READINESS SCOPE / METHOD OF IMPLEMENTATION SON OPERATIONAL READINESS MANAGER REPORTS TO SITE DIRECTOR AND

~

INTERACTS DIRECTLY WITH TINE ORGANIZATIONS ONSITE TO PERFORM THE' OPERATIONAL READINESS EVALUATION ELEMENTS:

1.

SON #UCLEAR PERFORMANCE PLAN IMPLEMENTATION A.

SAL CLOSURE B.

TEXT INTENTION CLOSURE C.

MAJOR PROJECT CLOSURE 2.

EVALUATION OF MANAGEMENT PERFORMANCE OBJECTIVES

~

AGAINST ESTABLISHED CRITERIA 3.

VERIFICATION THAT RESTART PREREQUISITES MET OS44H

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OPERATIONAL READINFSS EVALUATION CLOSURE STATUS I

1.A.

sat CLOSURE (PRIOR TO MODE 4) 520 SAL ITEMS REQUIRED FOR UNIT 2 RESTART 370 SAL ITEMS CLOSED 150 REMAIN TO BE CLOSED I

1.B.

TEXT INTENTION Cl0SURE (PRIOR TO MODE 4)

TOTAL DEEN

• CLOSED TEXT INTENTIONS IDENTIFIED AS RESTART

~10f 79 33 TEXT INTENTIONS IDENTIFIED AS POSTRESTART' 44 39 5

• THE REMAINING OPEN INTENTIONS CAN BE DIRECTLY TIED TO AN EXISTING OPEN SAL.

1.C.

NAJOR PROJECT CLOSURE REPORTS (PRIOR TO MODE 4) __.

~

CLOSURE CRITERIA DEVELOPED FOR ALL MAJOR PROJECT AREAS (22) 21 0F 22 MAJOR PROJECT CLOSURE REPORTS ISSUED RESTART ACTIVITIES IDENTIFIED IN REPORTS AND NOT CLOSED AT I

TIME OF REPORT ISSUANCE ARE SCHEDULED IN P/2-I RESTART ACTIVITIES OPEN AT REPORT ISSUANCE (166).--

~M RESTART ACTIVITIES OPEN TODAY (&8)

OPEN ITEMS TIED TO EXISTING SAL ITEMS l

0544H

________________-____a

2.

EVALUATION OF PERFORMANCE OBJECTIVES AGAINST ESTABLISHED CRITERIA FOR SON ORGANI7ATION 14 PERFORMANCE OBJECTIVES ESTABLISHED 1-4 CRITERIA ESTABLISHED FOR EACH PERFORMANCE OBJECTIVE A TOTAL OF 393 PERFORMANCE OBJECTIVES / CRITERIA - 0 ORGANIZATION COMBINATIONS ADDRESSED 0F THE 393 COMBINATIONS EVALUATED, 46 RESTART ACTIONS REMAIN TO BE COMPLETED-CLOSURE OF REMAINING-ACTIONS TO BE VERIFIED BY SAL CLOSURE OR OPERATIONAL READINESS STAFF PRIOR TO MODE 4 3.

STARTUP PREREQUISITE VERIFICATION

.__ l _

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CHECKLIST DEVELOPED (ATTACHMENT 1 To RTI-1.1, MASTER' TEST-SEQUENCE)

MANAGEMENT VERIFICATION THAT CHECKLIST ITEMS ARE RESOLVED FOR RESTART TO OCCUR JUST:

(1) PRIOR TO SYSTEM ALIGNMENT - SECTION 5

~

(2) PRIOR TO MODE 4 - SECTIONS 6, 7, 8, AND 91

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0544H

4 Or a

4 RESTART TEST PROGRAM W6 l

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RESTART TEST PROGRAM NRC INTERFACE 1'

-SUBMITTALS COMPLtizD ON PROGRAM.AND REQUIRED TESTING.

NRC TO PROVIDE INPUT TO NPP SER.

FUNCTION ANALYSIS. REPORTS AND TEST ANALYSIS REPORTS BEING PROVIDED TO NRC RESIDENT UPON APPROVAL BY JTG.

a l

4 TEST ANALYSIS REPORTS-WITH POST MODE 4 TESTING WILL BE COMPLETED PRIOR TO STARTUP (MODE 2).

ALL OTHER TEST ANALYSIS REPORTS WILL BN COMPLETED PRIOR TO RESTART (MODE 4).

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RESTART TEST PROGRAM PROGRAM STATUS FUNCTION ANALYSIS REPORTS

- 4872 FUNCTIONS REVIEWED i

1 j

- 37 FUNCTION ANALYSIS REPORTS WRITTEN

- 22 REPORTS APPROVED BY JOINT TEST GROUP SPECIAL TEST INSTRUCTIONS"

- 13 TESTS REQUIRED FOR MODE 4.

ONE TEST HAS BEEN

, CONDUCTED.

12, TESTS HAVE BEEN WRITTEN AND ARE IN THE REVIEW AND APPROVAL PROCESS.

- 4 TESTS REQUIRED FOR MODE 2.

~ ~~~ ~~

1,,

i SURVEII, LANCE INSTRUCTIONS i

- 130-SURVEILLANCE INSTRUCTIONS IDENTIFIED AND SCHEDULED i

AS PART OF PROGRAM.

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FUNCTION VALIDATION SYSTEM'NO.,22_,

NAME Containment'serav '.

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Provide.

CTMT HI HI SI-247.

SAT SAT SAT SAT SAT SAT SAT SAT SAT Tcmp & Press.

Pressure 900 Suppression Containment-Manual SI-247.

SAT SAT SAT SAT SAT SAT SAT SAT SAT 900 Pump 2A-A Flow SI-37 SAT SAT SAT SAT UNS' UNS SAT SAT SAT-

> 4750 gpm

~

discharge Prossure <

SI-37 SAT SAT SAT SAT UNS SAT SAT SAT SAT 140 psig I

Pump 2B-B Flow SI-37 SAT SAT SAT SAT UNS UNS SAT SAT SAT

> 4750 gpm diceharge I

Pressure >

SI-37 SAT SAT SAT' SAT UNS SAT SAT SAT SAT r

140 psig l

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CSS HI I)p lesz TVA-21 SAT SAT.

UNS UNS N/A SAT SAT SAT-SAT then 10 psid j

fer EX 2A & 23 5,

NPSH Pump 2A-A' W-6.1A1 SAT SA?

SAT SAT N/A --

SAT SAT SAT SAT NPSH Pump 2B 'B W-6.1A1 SAT 5AT SAT SAT N/A SAT SAT SAT ~

SAT ~

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RD1 ARKS:

SI-37 does not require pump flow of > 4750 gym [.i "_.

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.(2).. Ctmt, spray discharge orfices were modified.; Supp.orting cale* s' can't- -_

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1 (3) _ TECH. SPEC ' limit ;of-140 psis discharge pressureV s D'oes, notj ag' ee witF F r

Design Criteria, j N'

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.T 1%.7 M >':'

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,,,d.g; if N/A = Not applicable

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RESTART TEST PROGRAM FLNCTIONAL TEST MATRIX wa rtYAH LNIT 2 DNE DETERMINED FUNCTIONS TFRTGN CRITERIA I

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DISTRIBUTION FOR MEETING

SUMMARY

DATED:

August 26, 1987 Facility: Sequoyah Nuclear Plant, Units 1 and 2*

DocketJFile" NRC PDR Local POR Projects Reading l

l SQN Reading J. Keppler/J. Axelrad S. Ebneter/S. Richardson J. Zwolinski B. D. Liaw G. Zech RII S. R. Connelly.

EWS-461 J. Donohew E. McKenna J. Kelly Te Rotella C. Jamerson OGC-Bethesda MNBB-9604 F. Miraglia P-428 E. Jordan MNBB-3206

.J. Partlow EWS-360 ACRS-(10)

Hon. M. Lloyd Hon. J. Cooper Hon. A. Gore Hon. D. Sundquist l

Dr. Henry Myers Mr. R. King, GA0 P. Gwynn H-1149 l

T: Miller H-1149

(

J. Austin H-1149 J. Milhoan H-1149 C. Ader H-1149 TVA-Bethesda F ' Combs T. Rehm B. Pierson i

W. K. Poertner G. Hubbard J. Clifford M. Branch P. Harmon

• Copies sent to persons on facility service list l

- - -