ML18153A994
| ML18153A994 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/08/1994 |
| From: | Buckley B Office of Nuclear Reactor Regulation |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| TAC-M87312, NUDOCS 9407130313 | |
| Download: ML18153A994 (7) | |
Text
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- . t Docket No. 50-280 Mr. J. P. O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060
Dear Mr. O'Hanlon:
June 8, 1994 *
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE SURRY POWER STATION, UNIT 1, THIRD IO-YEAR INSERVICE INSPECTION (ISi} PROGRAM (TAC NO.
M87312)
The NRC staff with assistance from our contractor, Idaho National Engineering Laboratory (INEL}, is evaluating your July 16, 1993, submittal on the Surry, Unit 1 third IO-year ISi program.
Based on our evaluation, we find that additional information is required in order to complete our review.
It is requested that you provide responses to the questions delineated in the enclosure within 60 days of receipt of this letter.
In addition, to expedite the review process, please provide a copy of your response to our contractor, INEL, at the following address:
Boyd W. Brown ED&G Idaho, Inc.
INEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 This requirement affects fewer than 10 respondents and, therefore, is not subject to Office of Management and Budget Review under P.L.96-511.
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9407130313 940608 1*
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Enclosure:
Additional Information Request cc w/enclosure:
See next page OFFICE LA: PDil-2 PM:
NAME Elana £,ff BBu Sincerely, (Original Signed By)
Bart C. Buckley, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Distribution
_ Docket File PDil-2 RF NRC & Local PDRs SVarga GLainas HBerkow JStrosnider Elana OGC ACRS (10)
MPSiemien,OGC ESullivan TMclellan I...
DATE 07 /. /94 07 /
/94 07 / (g /94 OFFICIAL RECORD COPY - DOCUMENT NAME: C:\\AUTOS\\WPDOCS\\SURRY\\SU87312.LTR
Mr. J~ P. O'Hanlon Virginia Electric and Power Company cc:
Michael W. Maupin, Esq.
Hunton and Williams Riverfront Plala, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Mr. Michael R. Kansler, Manager Surry Power Station Post Office Box 315 Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Mr. Sherlock Holmes, 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 Post Office Box 1197 Richmond, Virginia 23209 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Robert B. Strobe, M.D., M.P.H.
State Hea 1th Cammi ss i oner.
Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Surry Power Station Attorney -General' Supre~e Court Building 101 Nor.th 8th Street Richmond, Virginia 23219 Mr. M. L. Bowling, Manager Nuclear Licensing & Programs Innsbrook Technical Cente.r Virginia Electric and Power Company 5000 Dominion Blvd.*
Glen Allen, *vifginia 23060
VIRGINIA EL~CTRIC AND POWER COMPANY SURRY POWER STATION, UNIT I
- . DOCKET NUMBER 50-280*
MATERIALS ENGINEERING BRANCH DIVISION OF ENGINEERING ENCLOSURE Request for Additional Information - Third IO-Year Interval Inservice Inspection Program Plan I. Scope/Status of Review Throughout the service life of a water-cooled nuclear power facility, 10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers {ASHE) Boller and Pressure Vessel Code Class I, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASHE Code Section XI, "Rules for Inservice Inspection of Nuclear Power Pl*nt Components", to the extent practical within the limitations of design, geometry, and materials of construction of the components. This section of the* regulations also requires that inservice examinations of components and system pressure tests conducted during the successive 120-month inspection interval shall
.. ~
comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.SSa(b) on the date 12 months prior to the start of a successive 120-month interval, subject to the limitations and modifications listed therein.
The components {including supports) may meet requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.SSa(b) subject to the limitations and modifications listed therein. The licensee, Virginia Electric and Power Company, has prepared the Surry Power Station, Unit 1, Third 10-Year Interval Inservice Inspection (ISI)
Program Pl an, Rev O to meet the requirements of the. 1989 Edition of Section XI of the ASME Code except that the extent and frequency of examination for 8-J piping welds has been determined by the 1974 Edition through Summer 1975 Addenda (74S75) as allowed by 10 CFR 50.SSa{b).
As required by 10 CFR 50.SS(g)(S), if the licensee determines that certain Code ~xamin*tion requirements are *impractical and requests relief, the licen*see shall submit information.to the Nuclear Regulatory Commission (NRC) to support that determination.
The staff has reviewed the available *information in the Surry Power Station, Unit 1, Third 10-Year Interval !SI Program Plan, Revision O; submitted July 16, 1993 and the requests for relief from the ASME Code Section XI requirements that the licensee has determined to be impractical.
- 2. Additional Information Required Based on the above review, the staff has concluded that tne following information and/or clarification is required in order to complete the review of the ISI P_rogram Plan:
A.
Table IWB-2500-1, Examination Category B-G-1, Note 3, requires selection of bolting on heat exchangers, piping, pumps, and valves for examination be limited to those components selected for examination under Examination Categories 8-8, 8-J, B-L-2, and B-M-2.
In review of pump bolting selected for inspection, the staff noted that the pump bolting selection was associated with B-L-1 versus B-L-2, as the 89 Edition of Section XI requires.
Please provide clarification and/or technical justification regarding the above discrepancy.
B.
Paragraph 10 CFR 50.55a(b)(2)(iv) requires that appropriate ASME Code Class 2 piping welds in the Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR) systems be examined.
The staff believes that piping welds in these systems should not be completely exempted from inservice volumetric examination based on Section XI exclusion criteria contained in Table IWC-2500-1.
In the review of-Class 2 piping welds selected for *examination, the staff noted-that a signific~nt humber of welds in the Coritainment
. Spray and Safety Injection systems are excluded from exam-ination based-on wall *thickness. For ~xample; ~11 welds in the Containment Spray System (CSS) on the discharge side of the containment spray pumps have been excluded from examination.
The CSS piping on the discharge side of the pumps is a critical part of. the system that i~
relied on to function during emergency conditions. This portion of the CSS contains stagnate oxygenated borated water, which has been found to be a major contributor to Intergranular Stress Corrosion Cracking in stainless steel piping.
To provide assurance *of_ the structural integrity of the thin-walled welds, the NRC recommends that licensees perform an augmented volumetric examination on a ~mall percentage, specifically 7 1/2% of welds in those portions of lines excluded from examination.
The licensee is requested to address this concern.
C.
Relief Request SR-003: Examination Category 8-D, Item 83.120 requires a 100% volumetric examination of the nozzle inside radius section of the pressurizer nozzles.
The licensee proposes a visual (VT-2) examination of the pressurizer surge line nozzle area to be performed during the normally scheduled pressure test (Class l} each refueling outage.
Paragraph IWA 2240, "Alternative Examinations", of the ASME Code Section XI states, "Alternative examination methods, a combination of methods, or newly developed techniques may be substituted for the methods specified in this Division, provided the Inspector is satisfied that the results are demonstrated to be equivalent or superior to those of the specified method".
The above mentioned Code-required examination (VT-2 visual during pressure test} is not considered an alternative examination.
Please provide additional information or an alternative examination that will ensure operational readiness of the subject examination areas.
- 0.
Relief Request SR-005:
The existing calibration blocks at Surry Power Station, Unit l, were designed and fabricated before the guidelines of ASME Section XI were developed ~nd approved~ Pleas~
provide a list of the ultrasonic calibration standards being used during the third IO-year interval ISI at Surry Power Station, Unit 1.
The list should include the calibration standard identifications, material specifications, sizes, and any variance from Code requirements.
E.
Relief Request No. 4: IW0-2500-1 requires a system hydrostatic test in accordance with IW0-5223, System Hydrostatic Test, for Class 3 pressure retaining piping.
The licensee stated that the Component Cooling Water System is utilized for cooling important safety-related components associated with the nuclear core.
In addition, the licensee states that portions of this system cannot be isolated, in most instances, without removing fuel totally from the core, and that this action would be time consuming and delay unnecessarily the refueling process. It appears that the required hydrostatic test could be done in conjunction with vessel inspections requiring total removal of th~
fuel.
Please provide further justification for*not performing the Code-required hydrostatic test.
E.
Relief Request No. 11: IWA-5242{a), states that for systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2.
The licensee states that insulation will be removed and a direct visual inspection for evidence of leakage at pressure-retaining bolting will be performed at the required frequency; however, the system/component may or may not be at pressure.
During a conference call held March 11, 1994, the licensee agreed to a four-hour pressure test hold time.prior to performing the VT~2 visual examination.
Please co~firm that the required VT-2 visual exami na:t ion will be performed at test pres*sure -after a 4-hour hold.
time at the require~ test pressure.
G.
Verify that there are no additfonal relief requests, other than those submitted JulY 16, 1993.
If additional relief requests are required, the licensee sliould subm.it them for staff review.
- The schedule for timely completion of this review requires that the licensee provide, by the requested ciate, the above requested information and/or clarifications regarding the Surry Power Station, Unit 1, Third 10-Year Interval !SI Program Plan, Revision 0.