ML20069A653
| ML20069A653 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna, 05000000, Shoreham |
| Issue date: | 05/14/1981 |
| From: | Albert Lee Office of Nuclear Reactor Regulation |
| To: | Rosztoczy Z Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082480769 | List: |
| References | |
| NUDOCS 8106010266 | |
| Download: ML20069A653 (7) | |
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UNITED STATES
[(} g '",,g NUCLEAR REGULATORY COMMISSION s
...E WASHINGTON O.C.20555 C
VAY 1 4 198I
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MEMCRANDUM FOR: Zoltan R. Rosztoczy, Chief Equipment Qualification Branch l
Division of Engineering i
l FROM:
Arnold Lee
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Equipment Qualification Branch Division of Engineering
SUBJECT:
TRIP REPORT FOR SEISMIC CRITERIA IMPLEMENTATION REVIEW MEETING WITH PENNSYLVANIA POWER AND LIGHT COMPANY (PP&L)
ON SUSQUEHANNA STEAM ELECTRIC STATION (SSES)
The Seismic Qualification Review Team (SQRT), consisting of engineers from the l
Equipment Qualification Branch (EQB) and the Brookhaven National Laboratory
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(BNL), made a visit to SSES at Berwick, Pennsylvania, on March 16-20, 1981.
The purpose of the visit was to conduct a plant site review of the qualification methods, procedures, and results for selected safety-related mechanical and electrical equipment and their supporting structures. The intent 1on was also to observe the field installation of the equipment, to validate the equipment f
model employed in the SSES qualification program.
The background, review procedures, findings and conclusions of the meeting, and the required followup actions are summarized below. A list of attendees at the conferences is contained in Attachment I, and a list of the equipment selected for audit is shown in Attachment II.
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1.
Backaround The applicant has described the equipment qualification program in Sections 3.9 and 3.10 of the Final Safety Analysis Report, consisting of dynamic testino 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 safe shutdown earthquake (SSE) specified for the plant. The applicant has also described the program for the qualification cf safety-related equipment for the combined seismic hydrodynamic vibratory loads associated with the MARK II containment suppression pool.
In instances where components have been qualified by testing or analysis to other than current standards such as Institute of Electrical and l
Electronics Engineers Standard, 344-1975, "Reccmmended Practices for Seismic Qualification of Class IE Equipment fur Nuclear Power Generating Stations," and Regulatory Guides 1.92, " Combining Modal Responses and Spatial Components in Seismic Response Analysis," and 1:100, " Seismic Qualification of Electric Equipment for Nuclear Power Plants," or where I
equipment is affected by and was not cualified for the suppression pool hydrodynamic loads, the apolicant has undertaken a reevaluation and recualification program.
1 XA Copy Has Been Sent to PDP3 I
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MAY I 1W 2-The applicant has identified those items of nuclear steam supply system j
ard balance-of-plant equipment requiring reevaluation, has described the methods and criteria used to detemine the acceptability of equipment
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qualification to meet the required dynamic _ loads, and has submitted lj the up-to-date reevaluation and requalification results.
M The plant site review was performed to determine the extent to which the qualification of equipment, as installed ir SSES meets the current licensing 8
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criteria as described in the Standard Review Plan (SRP) Sections 3.9.2 and ij 3.10.
Lj II. Review Procedures Prior to the site visit, the SQRT reviewed +.he equipment seismic qualification l
information contained in the pertinent FSAR section< and the reports referenced l'.
therein. A representative sample of 26 pieces of safety-related mechanical and electrical equipment, including both NSSS and B0P scopes as shown in Attachment II, were selected for the plant site review. Thi: selection includes 12 NSSS equipment and 14 BOP equipment. The review consisted of field observations of the actual equipment configuration and its installation, followed by the review of the corresponding test and/or analysis documents.
l Brief technical discussions were held during the review sessions to provide SQRT's feedback to the applicant on the equipment qualificntion. An exit conference was held on the final day, March 20, to sumarize and conclude l
the plant site visit.
III. Findinas and Conclusion The review team was informed at the beginning of the audit that among the 26 pieces of equipment selected, six of them had not been completely qualified to the rrquired hydrodynamic loads and therefore were not auditable. The SQRT was further informed of the fact that the applicants had completed the qualification for only 35 percent of the total safety-related equipment components for the required loadings. Although this low percentage is partly attributable to the status of motor-operated valves with f.IMITORQUE l
operators, whose requalification to seismic and hydrodynamic loads remains an outstanding issue for ali Mark II plants, we consider the extent of completion of the applicant's qualification program to be insufficient to draw anv conclusions with regard to the acceptability of all the safety-l related equipment. We have, therefore, infomed the applicants during the plant site audit that the review team will conduct an additional audit when the qualification program'is complete.
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The review team conducted the plant site review for the remaining 20 pieces l
of equipment which were available for audit. The review identified the need to clarify the details of the qualification for scme pieces of equipment.
The applicant has comited to submit additional information and clarification for a followup review prior to approval of plant operation. The equipment l
for which additional information is required and the spe:if'c items to be addressed are discussed in Section IV, Followup Actions, 4
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N'I Based on the results of the review to date, we conclude that in appropriate seismic and dynamic qualification program has been defined for the equipment i
j audited which will provide adequate assurance that such equipment will function properly during and after the excitation imposed by the Safe Shutdown Earthquake or hydrodynamic loads associated with discharges into the suppression pool, or 'by the combined eart:1 quake and hydrodynamic loads. Because of the extent of completion of the program, however, I
we cannot conclude that an appropriate overall oualification program has been implemented for all the safety-related mechanical and electrical equipment which will provide the same assurance of function-ability.
IV.
Followup Actions 4
In order to proceed with our review we have requeste:1 the applicant to provide the following information:
(1) Provide an updated list and the completion schedules for equipment which was not qualified at the time of the site visit.
(2) Provide the four-page review team summary forms for the nuclear steam system supplier equipment which was audited and the four-page summary forms for all the nuclear steam system' supplier and balance-of-plant equipment which was not qualified as identified in (1).
(3) For the valves audited, provide a comparison between the acceleration
'g' values used in the qualification and those obtained from the final as-built piping analysis.
(4) Provide the technical bases for concluding that none M the equipment will be damaped as a result of potential faticue cycling effects due to safety relief valve loadings.
(5) Provide clarifying details concerning the qualification of some pieces of equipment as listed in Attachment III, and detailed in BNL's evaluation report.
The review of the applicant's implementation of the equipment qualification
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program is continuing and the applicant is required to resolve all outstanding items as identified in Section IV above. As stated in Section III, the review team will conduct an additional audit when the qualification program is complete.
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Arnold Lee Equipment Qual fication Branch Division of Engineering
Enclosures:
As stated cc:
R. Vollmer M. Haughey W. Johnston R. Riggs R. Tedesco M. Stolzenberg B. Younablood A. Lee R, Stark M. Reich, BNL T. Y. Chang J. Singh, INEL R. LaGrange
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if ji ATTACHMENT 1 SQRT PLANT SITE AUDIT SUSQUEHANNA STEAM ELECTRIC STATION Plant Site Conference March 20, 1981 LIST OF ATTENDEES NRC General Electric Arnold Lee N. David Weiss N. G. Luria T. Y. Chang Geo. Heinold Jim Cleveland Brookhaven National Laboratory Clyde Nieh Daniel Hardesty i
John Curreri George Samstad Mano Subudhi Mim Mokri A. J. Philippacopoulos C. V. Subramanian Pennsylvania Power & Licht Company Bechtel R. W. McNamara W. S. Tseng R. H. Featenby P. Gupta F. Jackson G. H. Shah F. J. Lahovski R. Roberts P. W. Brady L. B. Pulley Rob Betslin R. C. Soderoholm R. A. Beckley O. A. Nossardi M. S. Gorski M. Castillo
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C. T. Coddington J. Hershey R. E. Moyer S. Hoopes G. Kalinowski j
Neil Covington 3
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m ATTAC}NENT II EQUIPMENT LIST FOR SORT PLANT SITE AUDIT
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/1.
E11 - C002 - RHR Pump / Motor
/2.
E41 - C001 - HPCI Pump i
/ 3.
H12 - Control Panel - Specifically, P601 4.
H23 - Control Panel - Specifically, P001 & P007 s 5.
E32 C001 -or E32-C002 - MSIV Blower i
s 6.
E51 - C001 - RCIC Pump e
/ 7.
E21 - C001 - Core Spray Pump Motor
' v 8.
B31 - F023 - Recirc Gate Valve
/ 9.
B21 - F013 Safety Relief Valve 4
- 10. H23 - P00ff - Reactor Vessel Level & Pressure Control Panel B sll. H23 - P010 - Jet Pump Local Panel B
/12. H12 - P700 - Tem Cabinea Assembly BOP l.
E-109 - 4KV Switchgear 2.
E-152 - Automatic Transfer Switch
/ 3.
J-3A - Field Mounted Electronic Pressure Transrritter
- 4. *J-05A - Control Panels - Specifically, IC-681 & 2C-681
/ 5.
M-ll - Emergency Water Pump 1
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- 6. *J-69 Pilot Solenoid Valve 4
/ 7.
M Engine Driven Water Pump
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M D-G Intake / Exhaust Expansion Joint i
/9 M Pre-Lube Pumo
- 10. *M-149 - Containment Vacuum Relief Valve
- 11. *M-159 - Nuclear Safety & Relief Valves - Specifically, PSV-E51 - IF017 j
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4 Attachment II - continued i e
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- 12. *P-12 (Part I) - Motor Operated Gate Valves 150# & 300#.
- 13. *P-148 - Motor Operated Gate Valve (2")
- 14. P-16 (Part II) Gear Operated Butterfly Valve (150#)
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- Equipment which had not been congletely qualified to the required hydrodynamic loads at the time of site audit.
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d ATTACINENT III SPECIFIC INFORMATION NEEDED FOR SOME EQUIPMENT
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E11-C002 - RHR Pump / Motor 1
, a) Provide reanalysis to show that the top motor bearing is not overstressed.
,, b) Pmvide resolution for the overstressed foundation bolts 2.
E32-C001 or E32-C002 - MSIV Blower n& f4 ? e* !!y A
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/ a) Provide an explanation of how the steel support frame is analyzed f
/ b) Provide assurance that the hold down bolts are adequately designed.
- 3. E51-C001 - dPump/ND f** O'* h a) Provide resolution for the overstressed top motor bearing o
4.
831-F023 - Recire. Gate Valve
?, a) Provide natural frequencies from the updated piping analysis being performed to reduce "g" loads at the discharge valve and bypass valve.l/rv ele'* # A 7, b) Provide "G" value at the gate valve obtained from the updated analysis.
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5.
B21-F013 - Safety Relief Valve a) Provide assurance that the structural integrity of the pipe welding ama e
around the valve will be maintained under the loadings considered.
6.
E-109 - 4KV Switchgear a) Provide a list of anamolies observed during the test and provide the
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I resolution action plan.
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/ b) Confim that HP analyzer had been calibrated for damping measurement
/ c) Provide natural frequency and the associated damping value table for review.
/ d) Provide en updated qualification report for review, which incorporates specific new paragraphs identified during the audit.
I J3A-Field Mourited Electronic Press Transmitter Q
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(i a) Provide infomation regarding the effecc on qualification of the manifold f
attached at the bottom of the support, aid the effect of small tubes
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connecting the transmitter and the manifold. Assess every transmitter throughout the plant for the similar effects.
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