ML20214S141

Summary of 861120 Mgt Meeting W/Util in Bethesda,Md Re Status of Sep.List of Attendees,Presentation Matl from Meeting & Agenda Encl

ML20214S141
Person / Time
Site:	Yankee Rowe
Issue date:	11/25/1986
From:	Mckenna E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-03-05.A, TASK-03-06, TASK-03-07.B, TASK-3-5.A, TASK-3-6, TASK-3-7.B, TASK-A-46, TASK-OR, TASK-RR NUDOCS 8612080199
Download: ML20214S141 (8)

Text

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.c . NOV 2 5 1986 o .

Docket No.50-029 LICENSEE: Yankee Atomic Electric Company (YAEC)

FACILITY: Yankee Nuclear Power Station

SUBJECT:

MEETING

SUMMARY

- NOVEMBER 20, 1986 On November 20, 1986, members of the NRC staff met with representatives of YAEC'in Bethesda, Maryland for a management meeting on the status of the Systematic Evaluation Program (SEP). The list of attendees is provided in Enclosure 1. Presentation material from the meeting, including the agenda, is in Enclosure 2.

During the past year, several technical review meetings have been conducted to resolve SEP issues, particularly for seismic and tornado events. .This meeting presented a management overview of progress on these issues and key issues yet to be resolved.

For the wind and tornado issues, a technical meeting on the remaining questions will be. held on November 21, 1986. Following this meeting, the staff expects to be able to complete the review in about two months. For Topic III-5.A, the staff is reviewing the licensee's recent submittal and 2 expects to issue any questions in December.

On Topic III-7.B. the remaining submittal from YAEC is expected by the end of November and the staff consultant's review will begin shortly thereafter.

Significant issues in the seismic reevaluation review (Topic III-6) were discussed as noted in the agenda. For the reactor pressure vessel, the analysis shows the potential for sliding under the NRC site specific loading.

During the May 1987 refueling outage, the licensee will more closely examine the configuration of the supporting structure to determine how to resolve this concern. The licensee has committed to demonstrate that sliding does not occur or to implement suitable plant modifications.

The staff has concluded during the technical review meetings that for the primary auxiliary building (PAB), the most appropriate representation of the response spectra is the envelope of analyses with frequency-dependent soil parameters for three soil depths. This envelope will be used by the staff for the confirmatory analyses of the PAB. The staff intends to judge the acceptability of licensee analyses for the turbine building frcm the results of the PAB; that is, if the PAB structure and piping and equipment can withstand the loading including the effects of soil-structure interaction, 8612090199 861125 9 DR ADOCK 0500

4 then the similar analyses for the turbine building would also be acceptable.

This issue will be further discussed at the final technical review meeting to the held in January 1987, when the confirmatory analyses results are available.

As part of the SEP review, anchorage of mechanical and electric equipment is being evaluated. The structural integrity of electrical equipment (i.e.,

internal load attachments) will be deferred to implementation of unresolved safety issue A-46.

The criteria to be used for the remaining seismic analyses were then discussed. The staff noted that if SEP guidelines or other " functional" criteria are used with the Yankee Composite Spectra input, case-by-case staff review would be necessary. However, YCS and code allowables or NRC spectra with SEP guidelines are acceptable approaches which would not require detailed staff review.

For the main steam / main feedwater support structure, the licensee plans to use NRC spectra input, PVRC damping, SEP guideline criteria and the multiple level response spectrum method. The staff cautioned that the recomendations for combinations in NUREG-1061 should be followed for such analyses.

The licensee provided a list of analyses that are yet to be completed for resolution of the SEP issues and the schedule for plant modifications. The modifications will be implemented in stages over the next few years. For instance, modifications to block walls in the turbine and primary auxiliary buildings are now complete. Pipe supports inside containment will be completed during the 1988 refueling outage. Modification of the main steam /feedwater support structure will also be done in the 1988 time frame.

The remaining modifications for which analyses are not yet complete will be implemented during a subsequent outage.

In summary, with present review schedules, the staff review of these SEP issues should be complete over the next few months, such that YAEC can proceed to complete all necessary plant modifications.

N Eileen M. McKenna, Project Manager Project Directorate #1 Division of PWR Licensing-A

Enclosures:

As Stated cc's: See Next Page

• SEE PREVIOUS CONCURRENCE Office: PM/ PAD #1 PD/ PAD #1 Surname: *EMcKenna/tg *Glear Date: 11/24/86 11/25/86 I

NOV 2 51988 Distribution Copies:

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NRC PDR Local PDR PAD #1 r/f PAD #1 s/f GLear EMcKenna 0GC-Bethesda EJordan BGrimes ACRS(10)

NRC Participants

-(cc: Licensee and Plant Service List)-

N L... . . . , , . . . ,

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s Mr. George Papanic, Jr.

. Yankee Atomic Electric Company Yur kee Nuclear Power Station CC:

Mr. James E. Tribble, President Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701 Thomas Dignan, Esquire Ropes and Gray

'225 Franklin Street Boston, Massachusetts 02110 Mr. N. N. St. Laurent Plant Superintendent Yankee Atomic Electric Company Star Route Rowe, Massachusetts 01367 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Resident inspector Yankee Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19<:6 Robert M. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 150 Tremont Street, 7th Floor Boston, Massachusetts 02111 n- - - , -

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l ENCLOSURE 1 NOVEMVER E0, 1986 MEETING ATTENCEES NAME AFFILIATION Eileen McKenna NRC/DPLA Chris Grimes NRC/ISAPD Pei-Ying Chen NRC/ISAPD Donald Hunter 'YAEC John D. H&seltine YAEC

. Michael Shulman CYGNA Bruce Holmgren _

YAEC George Papanic, Jr~. YAEC George Lear NRC/ PAD-1 Thomas Cheng NRC/ISAPE

V.

, ENCLOSURE 2 YANKEE ATOMIC ELECTRIC COMPANY U.S. NUCLEAR REGULATORY COMMISSION SEP MEETING AGENDA FOR YANKEE NUCLEAR POWER STATION NOVEMBER 20, 198G BETHESDA, MARYLAND

1. NRC SCHEDULE FOR RESOLUTION OF SEP TOPICS A. TOPIC III-2 WIND AND TORNADO LOADINGS B. TOPIC III-4.A TORNADO MISSILES C. TOPIC III-5.A EFFECTS OF PIPE BREAKS INSIDE CONTAIUMEliT D. TOPIC III-7.B DESIGN CODES AND SHOW LOADS E. NUREG-0325 IPSAR SUPPLEllENT

2. TOPIC III-6 SEISMIC DESIGN CONSIDERATIONS A. REACTOR PRESSURE VESSEL SLIDING B. SOIL-STRUCTURE INTERACTION C. FUTURE DESIGN CRITERIA D. CONPLETED MODIFICATIONS E. EQUIPl1ENT ANCHORAGE: SOUG APPROACH F. NRC SCHEDULE FOR RESOLUTION

3. YANKEE SCHEDULE FOR REMAINING SEP WORK A. ANALYSES B. PLANT MODIFICATIONS Y A N/0422AGEND3

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Yankee Nuclear Power Station Unresolved SEP Topics November, 1986 SEP Topic Responsible Engineer o' III-2 Wind and Tornado Loadings D. R. LeFrancois o II-2.A Severe Weather Phenomena D. R. LeFrancois o III-4.A Tornado Missiles B. W. Holmgren o III-5.A Effects of Pipe Breaks on R. G. Carter Structures, Systems, and Components Inside Containment o V-5 Par. 4.16 5 Leakage Detection R. G. Carter Required by Topic III-5.A Analysis o II-4.E Dam Integrity B. W. Holmgren o II-3.B Flooding Potential and Protection B. W. Holmgren Requirements.

o II-3.B.1 Capability of Operating Plant to B. W. Holmgren Cope with Design - Basis Flooding Conditions o III-6 Seismic Design Considerations Par 4.11.1 Structures D. R. LeFrancois Par 4.11.2 Piping Systems D. J. Fucito Par 4.11 3 Major Mechanical B. W. Holmgren Equipment and Supports Par 4.11.4 Electrical and Other D. R. LeFrancois Mechanical Components o II-4.A Tectonic Province B. W. Holmgren o II-4.C- Historical Seismicity Within 200 B. W. Holmgren Miles of Plant o III-7.B Design Codes, Design Criteria, Load J. E. Parker Combinations, and Reactor Cavity Design Criteria

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Yankee Nuclear Power Station Analyses To Be Performed After Resolution Of SEP November, 1986

1. Main steam /feedwater piping, supports,.and support structure outside

-containment (VC), including VC penetrations

2. Non-return valves (URV) enclosure .

3 Safe Shutdown System (SSS) piping and supports outside containment

4. Loops 2 and 3 mainsteam/feedwater piping inside containment 5 Reactor pressure vessel (RPV) sliding investigation / modification

6. Reactor missile. shield 7 Feed & Bleed heat exchanger supports and block wall enclosure

8. Block wall on west side of upper level PAB

9. Auxiliary boiler room roof and sections of the .PAB roof

10. Redesign two vertical supports in the Diesel Generator Building

11. Cable tray / conduit within the SSS scope 1

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