ML20032A456
| ML20032A456 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/29/1981 |
| From: | Albert Lee Office of Nuclear Reactor Regulation |
| To: | Rosztoczy Z Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20032A449 | List: |
| References | |
| NUDOCS 8110290613 | |
| Download: ML20032A456 (8) | |
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.....f dEF 2 31981 MEMORANDUM FOR: Zoltan R. Rosztoczy, Chief Equipment Qualificazion Branch Division of Engineering FROM:
Arnold Lee Equipment Qualification Branch Division of Engineering THRU:
Goutam Bagchi, Section Leader Equipment Qualification Branch Division of Engineering
SUBJECT:
TRIP REPORT FOR SEISMIC CRITERIA IMPLEMENTATION REVIEW MEETING WITH DETROIT EDISON COMPANY ON FERMI-2 The Seismic Qualification Review Team (SQRT), consisting of enginects from the Equipment Qualification Branch (EQB) and the Brookhaven National Laboratory (BNL), made a visit to Fermi-2 at Monroe, Michigan, on July 27-31, 1981. The purpose of the visit was to conduct a plant site audit of the qualification methods, procedures, and results for selected safety-related mechanical and electrical equipment and their supports. The intention was also to obserte the field installation of the equipment, to validate the equipment model. employed in the Fermf-2 qualification program.
The background, review procedures, findings and conclusions of the meeting, dnd the requWed followup actions are sumarized below. A list of attendees at the ronferences is contained in Attachment I, and a list of the equipment selecteo fo audit is shown in Attachment II.
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Baaground The applicant has described the equipment qualifica. ion program in Sections 3.9 and 3.10 of the Final Safety Analysis Report, consisting of testing and analysis, used to confirm the ability of safety-related mechanical and electrical (includes instrumentation, control and electrical) equipment and their supports, to function properly during and after the excitation imposed by earthquake loadings.
The plant site audit was performed to determine the extent to which the qualification of equipment, as installed in Fermi-2 meets the current licensing criteria as described in the Standard Review Plan (SRP) Sections 3.9.2 and 3.10.
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During the current staff review of the seismic input (see SER Sections 2.5.2 and 3.7.1), it was detennined that the shape of the original design response spectra for the Fermi-2 site is not consistent with that currently acceptable
- to the staff. The applicant was then required to develop site-specific response spectra for a reevaluation of structural and mechanical component design'and equipment qualification. The site-specific response spectra were reviewed by the staff and found acceptable (see Section 2.5.2. of SER supplement). This change in the input spectrum shape required that the resulting effect of the loading on the equipment be reassessed. As a result, we have determined to not only audit the applicant's original equipment qualification. program against the original response spectra, but also to audit his qualification' reassessment for the site specific spectra.
II. Review Procedures Prior to the site visit, the SQRT reviewed the equipment seismic qualification infonnation contained in the pertinent FSAR sections and the reports referenced therein. Twenty-four pieces of safety-related mechanical and electrical' equip-ment (See Attachment II) were selected.for audit against the original response spectra. Of the 24 selected equipment items,15-are in safe-shutdown systems and are part of the applicant's reassessment program. The audit therefore also included the review of the reassessment of these 15 pieces of equipment (See Attachment II). The plant site audit consisted of field observations of the actual equipment configuration and its installation, followed by the review of the corresponding test and/or analysis dcc uents. Brief technical discussions were held during the review sessions to provide SQRT's feedback to the applicant on the equipment qualification. An exit conference was held on the final day, July 31 to suninarize and conclude the plant site visit.
Qualification of torus-attached equipment under the effects of combined
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seismic and hydrodynamic loads was not reviewed in this audit. It is part of the applicant's Mark I Centainment Long-Tem Program, and will be completed and submitted for staff review before Augus t 1,1982.
III. Findings The applicant was notified at the beginning of the site audit that the 7 percent structure damping used in generating floor response spectra for aquipment reassessment is not acceptable because the stresses in critical structural elements obtained in building seismic' analysis reassessment are far below yield limit. For such a case, the staff concluded that an adequate str acture damping value is 5 percent (see Section 3.7.1 of SER supplement).
Although we proceedM with our review for equipment reassessment based on the spectrum curves of 7% structure damping value, we requested the applicant to perform 4n updated reassessment of the equipment qualification based on a 5% structure damping and submit the results for SQRT further review.
As a result of the audit, we identified concerns regarding the applicant's original equipment qualification as well as the reassessment due to site-specific respcnse spectra (see Section IV). The applicant has consnitted to submit additional information and clarification for a fol. low-up review prior to, approval of plant operation.
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Zoltan R. Rosztoczy 3-IV. Follow-up Actions In order to proceed with our review we have requested the applicant to provide the following information:
(1) Provide an updated list of equipment which was either not qualified or not installed at the time if SQRT Audit, by August 11, 1981.
(2) Provide a list of equipment contained in the Equipment Summary List which is oc longer considered safety related, by August 31, 1981.
(3) Provide the sumary results of the Equipment Seismic Qualification Reassessment based on the use of 5% structural damping instead of 7% and a table similar to _ Table 5.4-1 of July 15, 1981, submittal to NRC for components requiring requalification, by August 31, 1981.
In addition, provide a complete list of floor response spectra with respect to 5% structural damping, by August 31, 1981.
(4) At completion of Equipment Seismic Qualification Program-(including raassessment), provide a list of typical hardware modifications, for -
equipment both audited and not audited, which were found necessary 1
in order to meet the current licensing criteria, by September 1,1982 -
(3 inonths prior to issue of 0.L.).
(5) Provide confirmation for adequacy of acceleration values used in valve qualification by comparison with the results of As-built piping analysis for all types of valves audited, by Sectember 1,1982 (3 months prior to issue of 0.L.).
s (6) Provide SQRT fonns for all equipment which was either not qualified or not installed at the time of audit, by September 1,1982(3 months prior to issue of 0.L.).
(7) Provide clarifying details concerning the qualification of some pieces of equipment as listed in At.tachment III, and detailed in BNL's evaluation report.
V.
Conclusions Based on the results of the review to date, we conclude that an appro-priate seismic qualification program has oeen defined. The review of the applicant's implementation of the equipment qualification program is continuing and the applicant is required to resolve all outstanding items as identified in Section IV above.
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Arnold Lee Equipment Qualification Branch Division of Engineering Encl;sures: As stated cc: See next_page 4
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- 8. Youngblood M. Reich, 3NL-G. Bagchi J. Singh, INEL L. Kintner A. Lee.
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ATTACHMENT 1 SQRT PLANT SITE AUDIT Fermi 2 Plant Site Conference July 27 - July 31, 1981 LIST OF ATTENDEES NRC General Electric Arnold Lee Bernadette Bohn Sy Hassan R.L. Smith Brookhaven National Laboratory John Curreri Mano Subudhi
.A.J. Philippacopoulos P. Brown S. Sharma Detroit Edison Company Sargent & Lundy Wm. J. Fahrner George Hibet
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Walter M. Street B. Gogiwewi John Hankala M. Hassaballa Timothy J. 0keefe T. Fornek Shahan Kavafian H. A. Walter Hooper & Associates G.R. Overbeck L.J. Frasson David M. Hopper H.A. Balbale R.L. Buchholz S.P. Zoma R.L. Smith f
ATTAC MENT II EQUIPMENT LIST FOR -
Fermi 2 SORT Site Audit BOP Equipment Blde.
Mechanical l? Chilled Water Pumps (T41-00-C-041-FA-001)
Aux.
2*
10" Type 4340 Damper-(T41-00-F-900)-
3*
Engine Instrument Panel (R30-00-3-900-BA-003) RHR Complex 4*
Diesel Generator Service Water Pumps (R30-00-S-900-RA-005) 5*
RHR Mech. Draft Cooling Towers
-( El l-56-B-900-B A-003) 6*
24" 300# Globe Valve, WE SM-4-200 Motor Oper.
( A31 F-900-RA-029 )
Reactor 7.
4" 600# Y Globe Valve, Limit 52-0-40 Motor Oper. ( A31 00-F-900-RA-042)
Reactor 8.
20" Wafersphere Valve with Bettis Robotarm Actuator ( A31-00-F-900-RA-153)
Reactor 9*
Swing Check Valves 20", V12-2001', 2002, 2003, 2004, ( A31-01-F-900-RA-001)
Reactor 10* EECW Pumps Bil-93M (P44-00-C-001 A-RA-001)
Reactor
- 11. Floor Mounted Instrument Racks (H21-01-P-5018-RA-001)
Reactor
- 12. Remote-Shutdown Panel (C35-Pool)
Reactor 13* 480V SWGR Volt. Reg. - 1500KVA (R14-00-S-900-QL-031)
Aux.
14* Sattery Racks for 130 VDC battery (R32-00-S-900-RA-003)
Aux.
15* Nuclear Penetration Canister Assembly (T23-01-X-900-8A-008)
Aux.
NSSS Equipment Mechanical 16* Reactor Vessel Stabilizer (811-U002)
Reactor 17* Isolation Valve (821-F028) 18* Recirc. Discharge Valve (B31-F031) 19* Hydraulic Control Unit (Cll-0001)
Electrical 20. Barton Flow XMTR (831-N014A)
- 21. GE Relay (EllA-K001A)
Aux.
- 22. Bailey Diff Press (G33-ND41)
Reactor
- 23. GE Rack (H21-P025) i
- 24. Temp. Element (C41-N006)
- Equipment Reassessed
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ATTACHMENT III OpEN ITEMS: EQUIPMENT 3MCfFIC (1) Engine Instrument Panel, RHR Complex:_ 4 Items The Engine Instrument Panel is shock mounted on the support frame.
The clearance provided between the shock mounting and the support frame is 0.12".. Clearance of 0.16" minimum is required to prevent bottoming out of the shock spring. The clearance will be increascal as required by September 1, 1982-(3 months prior to issue of 0.L.).
(2) Diesel Generator Service Water Pumps:
Work needed to close out concerns arising from reassessment for site -
specific earthquake will be completed by September 1, 1982 (3 months' prior to issue of 0.L.).
(3) RHR Mechanical Drsft Cooling Towers: 4 Items The motor, the spray nozzles, and the fan have yet to be installed.
The work on placing of fill and eliminators is in progress. All,
work on mechanical draft cooling towers will be completed by September 1, 1982 (3 months p'rior to issue of 0.L.).
(4)
Floor Mounted Instrument Rack:
Instrument tubing / pipe supports have yet to be installed. This work will be completed by Seatember 1, 1982 (3 months prior to issue of 0.L.).
Orywell I & C pipe up to excess flow check valve wh'ich is outside the drywell and the tubing from there to the rack will be computer analyzed and appropriate supports designed and installed.
Other tubing attached to the rack will be designed as per DECO Design Spec. 3071-525 and S&L Report SL-3159.
(5) Hydraulic Control Unit:
Work on supports for tne attached piping will be completed by September 1, 1982 (3 months prior to issue of 0.L.).
(6) Barton Flow Transmitter:
Provide: 1) Bolt size and base plate dimensions as mounted on the panel;
- 2) Details of test mount cond.itions, and 3) ; Investigation of the device capability at resonance frequency ' f 30Hz in z-dirt:ction by August 31, 1981.
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G.E. Relay:
l Provide r (1 cation of Panel Hil.P617, by August 31, 1981.
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.cvide report (s) to show that resonance in side to side and vertical direction is higher than that in front to back direction by August 31, 1981.
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