ML18153A324
| ML18153A324 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/11/1998 |
| From: | Edison G NRC (Affiliation Not Assigned) |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| GL-87-02, GL-87-2, TAC-M69484, TAC-M69485, NUDOCS 9809180017 | |
| Download: ML18153A324 (6) | |
Text
i Mr. J. P. O'Hanlon Senior Vice President -
lear Virginia Electric and power Company 5000 Dominion Boulevard Glen Allen, VA 23060 September 11, 1998 e
SUBJECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (GL 87-02) (TAC NOS. M69484 AND M69485)
Dear Mr. O'Hanlon:
In your letter dated November 26, 1997, you provided a summary report in response to Generic Letter 87-02, related to seismic qualification of mechanical and electrical equipment.
The NRC staff is reviewing the summary report. Additional information (enclosure) is requested in order for the staff to complete its review. The enclosed request was discussed with Mr. Tom Shaub of your staff on September 4, 1998. A mutually agreeable target date of January 5, 1999, for your response was established. If circumstances result in the need to revise the target date, please call me at the earliest opportunity.
Docket Nos. 50-280 and 50-281
Enclosure:
Request for Addjtional Information cc w/encl: See next page DISTRIBUTION:
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PUBLIC PDll-1 R/F J. Zwolinski P. T. Kuo E. Dunnington G. Edison OGC ACRS
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L. Plisco, Region II Sincerely, Original Signed by:
Gordon E. Edison, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation DOCUMENT NAME: G:\\SURRY\\M69484-5.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy
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Mr. J. P. O'Hanlon September 11, 1998 e S~nior Vice President - *.
lear Virginia Electric and power Company 5000 Dominion Boulevard Glen Allen, VA 23060
SUBJECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2-REQUEST FOR ADDITIONAL INFORMATION REGARDING SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (GL 87-02) (TAC NO$. M69484 AND M69485)
Dear Mr. O'Hanlon:
In your letter dated November 26, 1997, you provided a summary report in response to Generic Letter 87-02, related to seismic qualification of mechanical and electrical equipment.
The NRC staff is reviewing the summary report. Additional information (enclosure) is requested in order for the staff to complete its review. The enclosed request was discussed with Mr. Tom Shaub of your staff on September 4, 1998. A mutually agreeable target date of January 5, 1999, for your response was established. If circumstances result in the need to revise the target date, please call me at the earliest opportunity.
Docket Nos. 50-280 and 50-281
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
- Docket File PUBLIC PDll-1 R/F J. Zwolinski P. T. Kuo E. Dunnington G. Edison OGC ACRS L. Plisco, Region II Sincerely, Original Signed by:
Gordon E. Edison, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation DOCUMENT NAME: G:\\SURRY\\M69484-5.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachmenUenclosure "E" - Copy with attachmenUenclosure "N" - No copy 1
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EDunnington C:,JT\\
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001
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Septe m ber 11, 1998 Mr. J. P. O'Hanlon Senior Vice President - Nuclear Virginia Electric a*nd power Company 5000 Dominion Boulevard
- Glen Allen, VA 23060
SUBJECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (GL 87-02) (TAC NOS. M69484 AND M69485)
Dear Mr. O'Hanlon:
In your letter dated November*26, 1997, you provided a summary report in response to Generic Letter 87-02, related to seismic qualification of mechanical and electrical equipment.
The NRC staff is reviewing the summary report. Additional information (enclosure) is requested in order for the staff to complete its review. The enclosed request was discussed with Mr. Tom Shaub of your staff on September 4, 1998. A mutually agreeable target date of January 5, 1999, for your response was established. If circumstances result in the need to revise the target date, please call me at the earliest opportunity.
Docket Nos. 50-280 and 50-281
Enclosure:
Request for Additional Information cc w/encl: See next page Sincerely, ~
p Gordon E. Edison, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
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e Mr. J.P. O'Hanlon Virginia Electric and Power Company cc:
Mr. Michael W. Maupin, Esq.
Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Mr. E. S. Grecheck Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, Virginia 23209 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Robert B. Strobe, M.D., M.P.H.
State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Surry Power Station Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. J. H. McCarthy, Manager Nuclear Licensing & Operations Support Innsbrook Technical Center Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. R. C. Haag U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. W. R. Matthews Site Vice President North Anna Power Station Virginia Electric and Power Company P. 0. Box 402 Mineral, Virginia 23117
e REQUEST FOR ADDITIONAL INFORMATION SURRY POWER STATION UNITS 1 & 2 USI A-46
Reference:
Letter from James P. O'Hanlon (VEPCO) to NRC (Document Control Desk),
"Virginia Electric and Power Company Surry Power Station Units 1 and 2 Summary Report for Resolution of Unresolved Safety Issue (USI) A-46," dated November 26, 1998.
- 1.
In Section 10, "Significant and Programmatic Deviations From the GIP," of the referenced submittal, the seismic margin methodology described in the EPRI report NP-6041, including the use of High-Confidence-of-Low-Probability of Failure (HCLPF) capacity, was used to verify the seismic adequacy of some equipment items, including tanks and heat exchangers. The conservatism of the above methodology is not certain when compared to the GIP-2 guidelines. Its application is, therefore, not endorsed by the NRC for the analysis of safety-related systems and components, including the resolution of USI A-46 mechanical, electrical, and structural component outliers. You are requested to reevaluate the portion of your USI A-46 program where such methodology has been employed, to ensure that the method of evaluation conforms to the GIP-2 guidelines or is otherwise acceptable to the staff.
- 2.
Provide the current resolution status for the identified outliers and plant installation deficiencies, including, but not limited to, those listed in Table 11.2-1 of the referenced submittal.
- 3.
In an attachment to the referenced submittal, the peer review walkdown report identified a number of concerns related to installation deficiencies. You are requested to elaborate on your actions to address and satisfactorily resolve the identified concerns.
- 4.
It is stated in the referenced submittal that for all buildings and elevations where SSEL equipment is located in the Surry plant, the in-structure response spectra (ISRS) are enveloped by the Reference Spectrum or the 1.5x8ounding Spectrum of the GIP. You are requested to provide the ISRS at the highest elevations, where SSEL equipment items are located in each building, and demonstrate their enveloping by the Reference Spectrum.
- 5.
Section 4.4.1 of GIP-2 states that all accessible anchorages should be visually inspected. State whether you have visually inspected all accessible anchorages. If not, provide your reasons for not doing so.
- 6.
State whether you have performed a tightness check on anchorages in accordance with GIP-2 provisions and what sampling method was used.
Enclosure
- 7.
State whether you have performed inspections for "Gap at Threaded Anchors" (check 6 of GIP-2), "Spacing between Anchors" (check 7 of GIP-2), "Edge Distance" (check 8 of GIP-2), "Concrete Strength and Condition" (check 9 of GIP-2), "Concrete Crack
- Locations and Sizes" (check 1 O of GIP-2), "Essential Relays in Cabinets" (check 11 of GIP-2), "Base Stiffness and Prying Action" (check 12 of GIP-2), and "Embedment Steel and Pads" (check 14 of GIP-2). If yes, describe your inspection procedures and results of the inspection.
- 8.
Identify all your large flat-bottom vertical tanks and heat exchangers and describe your procedures and criteria for verifying the adequacy of the tank shell buckling capacity (section 7.3.3.3 of GIP-2), anchorage capacity (sections 7.3.3. and 7.3.4 of GIP-2), and anchorage connection capacity (section 7.3.3.2 of GIP-2), and submit one sample calculation that demonstrates the adequacy of each of the above three capacities.
- 9.
In reference to item No. 1, you are requested to verify the seismic adequacy of the charging pump seal cooling tanks and refueling water storage tanks by performing a deterministic analysis, in accordance with the GIP-2 methodology, and submit the analysis results for staff review.
- 10.
It is stated in the referenced submittal that buried tanks are not sensitive to seismic inertia effects and you used that argument to dispose of the outliers associated with the underground fuel oil storage tanks and emergency condensate make-up tanks. Provide sufficient technical bases to verify the adequacy of these tanks taking into account the effects of wave passage and the resulting soil pressure.