IR 05000410/1986007
| ML20199H240 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/26/1986 |
| From: | Imbro E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20199H231 | List: |
| References | |
| 50-410-86-07, 50-410-86-7, NUDOCS 8604090319 | |
| Download: ML20199H240 (26) | |
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U.S. NUCLEAR REGULATORY n MMISSION OFFICE OF INSPECTION AND ENFORCEMENT Division of Quality Assurance, Vendor, and Technical Training Center Programs Report No.:
50-410/86-07 Docket No.:
50-410 Licensee:
Niagara Mohawk Power Corporation Facility Name:
Nine Mile Point, Unit 2 Inspection At:
Stone & Webster Engineering Corporation, Cherry H.ill, NJ Inspection ~ Dates:
January 3, 1986 January 7, 1986 Inspection Team:
Team Leader:
E. Imbro, Section Chief, IE Mechanical Systems:
T. DelGaizo, Ccasultant, WESTEC Services Mechanical Components:
J. Blackman, Consultant, WESTEC Services Electrier.1 Power /
Controls Discipline:
G. Morris, Consultant, WESTEC Services Civil / Structural:
A. Unsal, Consultant, HARSTEAD Engineering 3!/9 !/[
Prepared By:
Eugene V. Imbro Date /
Chief, Licensing Section Quality Assurance Branch, IE
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GATJd4nkr~um
/Datf Chief, Quality Assurance Branch a
8604090319 860326 PDR ADOCK 05000410 PDR:
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NINE MILE POINT, UNIT 2 ENGINEERING ASSURANCE TECHNICAL AUDIT No. 50 RESULTS AND CORRECTIVE ACTIONS SUPPLEMENTAL INSPECTION JANUARY 3 AND JANUARY 7, 1986 1.
Background In a submittal dated August 8,1985, Niagara Mohawk Power Corporation (NMPC) forwarded to the NRC the report of the Engineering Assurance Audit No. 50, which documented the results of the audit performed by Stone & Webster Engineering Corporation (SWEC) on Nine Mile Point Unit 2..From August 12 through August 16, the NRC conducted an inspection of the completed review plans and the audit backup information which was documented in Inspection Report 50-410/85-28, dated September 12, 1985. Due to the number of items which remained unresolved following the NRC Inspection, NMPC was requested to submit a supplemental report to address the. remaining open items. On September 27, 1985, l
NMPC submitted the Supplement to Audit Report No. 50.
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Purpose
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The purpose of this inspection was to review audit results and corrective action items which remained unresolved from the previous NRC inspection as documented in NRC Inspection Report 50-410/85-28.
Followit g review of NMPC's Supplemental Response, the following activities were conducted to ensure that all items in the NRC Inspection Reports were adequately addressed:
(1) verify that all NRC Inspection Report concerns were addressed; (2) review of backup documentation to verify that it supports the conclusions of the Supplemental Response; and (3) review the resolution of the remaining open items for acceptability.
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NRC Inspection Team This inspection was conducted by NRC personnel, with support of contractor personnel as follows:
Assignment Name, Position Team Leader E. Imbro, Senior Inspection Specialist, IE Mechanical Systems T. Del.Gaizo, Consultant, WESTEC Services Mechanical Components J. Blackman, Consultant, WESTEC Services Electrical Power /
G. Morris, Consultant, WESTEC Services Controls Civil / Structural A. Unsal, Consultant, HARSTEAD Engineering 4.
Personnel Contacted A number of NMPC and Stone & Webster Engineering Corporation (SWEC)
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perscnnel were contacted throughout the inspection. The following is a listing of key personnel contacted:
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Name Organization Position
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A. Capozzi SWEC Asst. Chief Engineer, EA R. Twigg SWEC Audit Team Leader C. Terry NMPC Licensing Manager W. Pananos SWEC Structural Auditor G. Arena SWEC EMD Auditor G. Bushnell SWEC Hazards Auditor E. Motlola SWEC EMD Auditor W. Nowicki NMPC Electrical Auditor R. Heine SWEC Controls Auditor A. Gwal SWEC NMP2 Electrical Manager J. A1 dredge SWEC Engineering Assurance A. Canuso SWEC Engineering Assurance 5.
General Conclusions Attachment 1 provides the disposition of inspection items identified in-NRC Inspection Report 50-410/85-28 dated September 12, 1985.
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Attachment:
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Status of Prior NRC Inspection - NRC Results and Corrective Actions Inspection Report 50-410/85-28 of September '.2, 1985.
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ATTACHMENT 1
STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS INSPECTION REPORT 50-410/85-28 0F SEPTEMBER 12, 1985
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Action Item No.
Subject Status Original Comment (C)/ Resolution (R)
CONTROLS DISCIPLINE E-C15-0 Set Point Calcula-CLOSED C: Verification must be made that (Previously referenced tions procedures are implemented as Item No. 5.2 -
which ensure test instrument
Inspection Report
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Inspection Report
a number of " Closed-Out" 50-410/85-12)
calculations for each actior; item which verified that the i
affected calculations had been
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properly updated. This review
adequately aadresses the NRC
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team's concerns.
General Item Supplement to Selection of Additional CLOSED C: The NRC team was concerned that Audit Report Pipe Supports for Review the pipe supports originally No. 50 -
reviewed did not represent
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Parrgraph 6.3.2 typical supports associated with the Reactor Core Isolation l
Cooling Systems (ICS).
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ATTACHMENT 1 - (Continued)
STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS INSPECTION REPORT 50-410/85-28 0F SEPTEM5ER 12, 1985
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Action Item No.
Subject Status DrigInal Comment (C)/ Resolution (R)
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Pera. 6.3.2 (Cont'd)
P.: The EA team. reviewed an additionalfive(5) pipe support calculations w.iich were more structurally complex than those originally selected and were representative of the type of support associated with the ICS System. The NRC team reviewed the checklists and other relevant documentation and is satisfied that the matter has been adequately addressed.
POWER DISCIPLINE E-P07-1
'The Need to Provide CLOSED C:
Provide additional details E-P10-0.
Additional Technical relative to safety significance E-P16-0 Information and design process effective-ness for the tabulated action E-P27-0 items.
E-P29-0 E-P31-0 R:
Detailed technical evaluations were provided for each item E-P37-0 which when reviewed by the NRC team satisfactorily resolved the original concerns. These discusriens included the effects of required hardware
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ATTACHMENT 1 - (Continued)
STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS INSPECTION REPORT.50-410/85-28 0F SEPTEMBER 12, 1985 Action Item No.
Subject Status.
Original Comment (C)/ Resolution (R)
changes and an evaluation of E-P07-1, etc. (Cont'd)
the overall design process effectiveness in light of the significance of the action items.
E-P21-0 Pump ICS*P2 Recircu-CLOSED C: The EA team must confirm that a lation Loop Heat procedure or suitable program exists to ensure that Dissipation keep-fill pump heat can be adequately dissipated during post-startup testing.
R: The Project developed a Change Package Notice to the
" Exception Restraint List",
which ider.tifies the need to monitor the heat dissipation associated with pump ICS*P2.
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The NRC team reviewed the associated documentation and is satisfied that it
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adequately addresses the original concerns.
E-P38-0 Localized Steaming CLOSED C: The EA team must confirm that a from Open Equip-procedure or suitable program is in effect to monitor ment Drains
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ATTACHMENT 1 - (Continued)
STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS INSPECTION REPORT 50-410/85-28 0F SEPTEMBER 12, 1985 Action Item No.
Subject Status Original Comment (C)/ Resolution (R)
E-P38-0 (Cont'd)
possible centamination from l
open drain funnels following plant startup, R: The Project developed and the
EA team reviewed an ALARA status sheet for this item.
This corrective action provides formal tracking of the item to ensure ultimate disposition by the ALARA review committee.
Since the potential for contamination is considered low this response is appropriate.
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The NRC team Sas reviewed the associated documentation and is satisfied that the matter has been properly addressed.
General Items Supplement to Audit High-Energy-Line-Dreak CLOSED C: The safe-shutdown portion of RGpert No. 50 -
inc HMP-2 HELB prog = was held Paragraph 6.3.4 opes: since that pertion of the program had not been implemented at the time of the last report.
R: The safe-shutdown partion of the HELB program has r.ow been
revi2wed by the EA t'eam.
An
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action item (E-M25-0) was issued related to single-failure considerations in the containment
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ATTACHMENT 1 - (Continued)
STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AMD CORRECTIVE ACTIONS INSFECTION REPORT 50-410/85-28 0F SEPTEMBER 12, 1985 Ac2ior. Ites No.
Subject Status Original Comment (C)/ Resolution.(R)
Para. 6.3.4 (Cont'd)
isolation aspects of a nitrogen line break to the ' ADS valves.
This item was satisfactorily
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resolved and further reviews indicated that single fai' lure was properly consioered in q
sucsequent safe-snutdown reviews. Tne NRC team reviewed decumentation 1)
f associated with this matter swo'
considers it closed.
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ATTACHMENT 1 - (Continued)
STATUS OF PRIOR A'RC INSPECTION - WRC -RESUI.TS AND CORRECTIVE ACTIONS IMSPECTION REPORT 50-410/85-28 0F SEPTEMBER 12., 1985 Action Item No.
Subject Status Original Comment (C)/ Resolution (R)
E-P55-0 HVAC Zone Temp CLOSED C: haximum zone temperatures cal-E-E36-0 Calculations culated for the reactor building were based on average cooling water temperatures.
The effect of using maximum temperatures should be evaluated.
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As a result of this concern, Action Items E-P55-0 and E-E36-0 were issued.
The resolution of,the action items involved a revision to the HVAC zone temperature calculation for the reactor building using maximum cooling water tempera-tures.
All zones were then reviewed for the impact of the changes on the qualification status of any hardware.
The final action involved the revision to certain specifications in order to provide consistency with the revised calculation.
Based on the NRC team's review of associated documentation, this matter is considered closed.
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l ATTACHMEMR 1 - (Continued)
STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS INSPECTION REPORT 50-410/85-28 0F SEPTENBER 12, 1985 Action Item No.
Subject Status Original Comment (C)/ Resolution (R)
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E-P54-0 RCIC Line Sizing CLOSE0 C:
A review of calculation
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A10.1-H-8, R/3 revealed an error in the way the flow resistance co efficient (K-factor) was determined from the valve vendor supplied flow coefficient (Cv).
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As a result of this concern, action item E-P54-0 was issued.
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The Project reviewed all QA Category I calculations in which Cv to K or K to K conve'r-
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sions were applied.
Five additional calculations with errors were uncoverkd, although
only the original calculation
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A10.1-H-8 was such that a chacpe to the size of the crifice was required, 'All calculations have been revised
end a replacement orifice in
the -case of calculation A10.1-H-8 has been obtained.
This item is considered to be c'iosed.
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STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS INSPECTION REPORT 50-410/85-28 0F SEPTEMBER 12, 1985 Acticn Item No.
Subject Status Original Comment (C)fResolution (R)
CIVIL / STRUCTURAL
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DISCIPLINE E-503-0 Control and Diesel Generator CLOSED C:
The Project's technical Building Stability Analysis justification for accepting a factor-of-safety against sliding less than the allowable
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is not acceptable.
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The Project has revised calculation C58-TAB 21 to include the effect of adhesion between the rock surface and the fill concrete. By using an adhesion stress of 15 psi, they
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have demonstrated that the
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factors-of-safety against sliding at the rock surface are above those required by the FSAR. They have also shown
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that sliding will not occur at the interface between the fill concrete and the bottom of the-mat.
Therefore, this action item is closed.
E-504-01 ICS Cubicle Water-CLOSED C:
An inconsistency exists and tight Door Design-QA must be resolved between the QA Category Conflict categories referenced in specifications P306C and S203C both of which are referenced in the governing design documents for the ICS Cubicle Watertight Door.
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ATTACHMENT 1 - (Continued)
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STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS
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INSPECTION REPORT 50-410/85-28 0F SEPTEMBER 12, 1985
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Action Item No.
Subject Status Original Comment.(C)/ Resolution (R)
E-SO4-01 (Cont'd)
R:
The Project has finished the review of SWEC specifications P306C and S203C.
All penetration seals were qualified as QA Category I, as required by specification P306C.
It was not possible to qualify the waterstops as QA Category 1, as required by specification S203C.
Therefore, all waterstops were downgraded to QA Category II, with the exception of two areas where they are required to be QA Category I.
For these areas, E&DCR 278571 was written to provide modification to isolate the water stops from environmental exposure. The Staff agrees with this resolution and considers this item to be closed.
E-S09-0 Design Requirements for CLOSED C: The structural qualification Special Doors-Specifica-of the door is dependent upon tion S208G the use of a higher than code allowable stress.
This can only be achieved by determination of actual yield stress for the steel used to fabricate it.
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ATTACHMENT 1 - (Continued)
STATUS OF PRIOR NRC INSPECTION - NRC RESULTS AND CORRECTIVE ACTIONS
INSPECTION REPORT 50-410/85-28 0F SEPTEMBER 12, 1985
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Action Item No.
Subject Status Original Comment (C)/ Resolution (R)
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R: The Project has performed an E-509-0 (Cont'd)
analysis of door R328-7 using the mill test yield stress of 55 ksi. This analysis shows that the door is structurally adequate for the loads imposed on it.
The Staff agrees with this resolution. Therefore, this action ites is closed.
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E-S23-0 Cable Tray Base Plate CLOSED C: The EA team must verify that an Anchor Bolt Holes analysis has been done to show that prying forces are insignificant for the subject installation.
R:
Additional information provided by the Project shows that the prying forces for the anchor bolts, as mentioned in N&D 6532, are zero.
Also, this was an isolated case where the
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effects of prying were not considered in design. The NRC inspection team reviewed SWEC Calculation NM(C)-MS-4021,
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which shows that prying effects are considered. Therefore, i
this action item is closed.
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