IR 05000245/1985030

Insp Repts 50-245/85-30 & 50-336/85-35 on 851118-22.Major Areas Inspected:Licensee Implementation of Program Per Requirements of 10CFR50.49 for Establishing Qualification of Electric Equipment.Three Deficiencies Noted

ML20198K066
Person / Time
Site:	Millstone
Issue date:	04/02/1986
From:	Potapovs U, Wilson R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:
Shared Package
ML20198K059	List: IR 05000245/1985030 ML20198K054
References
50-245-85-30, 50-336-85-35, NUDOCS 8606030320
Download: ML20198K066 (14)

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No.: 50-245/85-30; 50-336/85-35 Docket No.: 50-245; 50-336 License No.: DPR-21; DPR-65 Licensee: Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141 Facility Name: Millstone Nuclear Power Station, Unit Nos.1 and 2 Inspection At: Berlin and Waterford, Connecticut Inspection Conducted: November 18 to 22, 1985

. l Inspector: Ed4- s .kFMld ib./ k ~1-d R. C. Wilson, Equipment Qualification & Test Engineer Date Also participating in the inspection and contributing to the report were:

U. Potapovs, Chief, Equipment Quali#ication Inspection Section, IE S. Alexander, Engineer, IE H. Walker, Engineer, NRR E. R. Richards, Member of Technical Staff, Sandia National Laboratories V. J. Dandini, Member of Technical Staff, Sandia National Laboratories R. A. Borgen, Consultant Engineer, Idaho National Engineering Laboratory L. Cheung, Reactor Inspector, RI M. J. Schaeffer, Reactor Inspector, RI

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I Approved by: db h %Y -

4-2-k U. Potapovs, Chief, Equ'pment Qualification Section, Date

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Office of Inspection and Enforcement 8606030320 86041" PDR ADOCK 05000245 G PDR I

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INSPECTION SUMMARY Inspection on November 18 to 22,1985 (Inspection Report No. 50-245/85-30; 50-336/8S-35)

Areas Inspected: Special, announced inspection to review the licensee's implementation of a program per the requirements of 10 CFR 50.49 for establishing and maintaining the qualification of electric equipment within the scope of 10 CFR 50.4 Results: The inspection determined that the licensee has implemented a program to meet the requirements of 10 CFR 50.49, except for certain deficiencies listed belo Report Name Paragraph Item Number (s)

Potential Enforcement / Unresolved Items: Limitorque operator wiring 4.D(1) 50-245/85-30-1; 50-336/85-35-1 Documentation deficiencies /85-30-2; 50-245/85-30-3 Limitorque terminal block 4.D(1) 50-245/85-30-3 Open Items: Replacement equipment procurement /85-30-4; 50-336/85-35-3 Completion of maintenance program /85-30-5; 50-336/85-35-4

' Solenoid valve wiring 4.D(2) 50-2a5/85-30-6 Conduit weep holes 4.D(3) 50-245/85-30-7 Motor maintenance requirements 4.D(4) 50-245/85-30-8; 50-336/85-35-5 l

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DETAILS 1. PERSONS CONTACTED 1.1 Northeast Nuclear Energy Company (NNECO)

, *E. J. Mroczka, Vice President - Nuclear Operations

• R. P. Werner, Vice President - Generation Eng. & Const *J. R. Ferraro, Manager - Generation Electrical En *A. Roby, System Manager - Generation Engineering

• P. A. Blasioli, Licensing Engineer

• J. A. Summa, Asst. Engrg. Supv., Millstone 1

• L. Johnson, Director, Generation Engineering & Design

• W. D. Romberg, Station Superintendant, Millstone

• B. Tuthill, Supervisor, Generation Electrical Engr *1. S. Nicosia, Engineer, Electrical Equipment Quali *W. H. Becker, Supervisor, Generation Electrical Engr *D. C. Nordquist, Manager, QA

• R. Ditman, Manager, Generation Electrical Engr *S. E. Scace, Superintendant, Millstone 2

• R. M. Kacich, Licensing Supervisor D. J. Odland, Engineering Supervisor, Millstone 1 R. L. Peterson, Assistant Maint. Supervisor, Millstone 1 D. W. Clark, I&C Engineer, Millstone 2 R. S. Peterson, Engineer, Electrical Equipment Quali R. W. Bates, Assistant Engrg. Supervisor, Millstone 2 D. C. Kross, I&C Supervisor, Millstone 2 E. Abolafia, Engineer, Nuclear Operations W. H. Becker, Nuclear Engineer, Nuclear Operations G. R. Pitman, Manager - Generation Electrical Engr G. A. Sauer, Electrical Engineer, Millstone 1 E. Olszewiski, I&C Engineer, Site G. Closius, QA Supervisor, Site C. Wargon, Maintenance Engineer, Millstone 1 J. Emery, QA Engineer F. C. Libby, QA Supervisor R. Bonner, Maintenance Enginee:

J. D. Stansbury, Electrical Maintenance Supervisor R. Salem, I&C Engineer M. Welker, I&C Instructor, Millstone 1 1.2 Consultants to NNECO P. M. Thaker, Engineer, Impell W. C. Lynch, Engineer, Impell 1.3 Observer R. K. Ho, EPM, Consultant to Nuclear Utility Group on EQ 1.4 NRC D. B. Osborne, NRR Millstone 2 Project Manager

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• Denotes those present at exit meeting in Berlin on November 22, 1985

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2. PURPOSE The purpose of this inspection was to review the licensee's implementation of a program meeting the requirements of 10 CFR 50.49 for Millstone Nuclear Power Station, Unit Nos.1 and . BACKGROUND The NRC held a meeting with NNEC0 on April 10, 1984 to discuss the licensee's proposed methods to resolve the EQ deficiencies identified in the SEPs dated December 13, 1982 for Unit I and April 6,1983 for Unit 2, and in the FRC TERs dated May 28, 1982 for Unit 1 and February 21, 1983

for Unit 2. Discussions also included NNEC0's general methodology for i compliance with 10 CFR 50.49 and Justification for Continued Operation (JCO) for those equipment items for which environmental qualification was not completed. Minutes of the meeting and proposed methods of resolution for each of the EQ deficiencies were documented in licensee submittals dated February 11 and April 9,1985 for Unit 1 and December 18, 1984 for Unit 2. Final SERs transmitted July 30, 1985 for Unit I and March 20, 1985 for Unit 2 identified that certain equipment in both units was still under JCO. By the time of the inspection the only equipment remaining under JC0 were eleven Limitorque valve operators in Unit 1; licensee submittals dated September 30 and October 29, 1985 requested further extension of the qualification deadline for these eleven valve operators. An NRC memorandum and order dated November 20, 1985, requires that after the staff completes evaluatioq of these eleven operators as part of the Integrated Safety Assessment Program, NNEC0 must replace any operators requiring replacement during the first outage of sufficient duration and no later than August 30, 198 . FINDINGS The NRC inspectors examined the licensee's program for establishing the qualification of electric equipment within the scope of 10 CFR 50.49. The program was evaluated by examination of the licensee's qualification documentation files, review of procedures for controlling the licensee's EQ efforts, verification of adequacy and accuracy of the licensee's 10 CFR 50.49 equipment list, and examination of the licensee's program for maintaining the qualified status of the covered electrical equipmen Based on the inspection findings, which are discussed in more detail below, the inspection team determined that the licensee has implemented a program to meet the requirements ot' 10 CFR 50.49 although some deficiencies were identifie E0 Program Procedures The inspectors examined the implementation and adequacy of the licensee's EQ program for establishing and maintaining the environ-mental qualification of electrical equipment in compliance with the requirements of 10 CFR 50.4 The following procedures were reviewed:

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- NE0 2.21 " Nuclear Plant Environmental Qualification Program" Revision 0, dated October-30, 198 NUSCO Branch Instructions GE-EQ-01, " Environmental Qualification Program for Millstone Units 1 and 2" Revision 0, dated October 11, 198 NE0 6.02 " Preparation and Review of Quality Pelated Purchase Requisitions" Revision 2, dated August 23, 198 Administrative Control Procedure ACP-QA-2,16 " Nuclear Plant Environmental Qualification Program" Revision 0, dated November 8, 198 NEO 3.03 "Preparatioe, Review, and Disposition of Plant Design Change Requests" Revision 4A, dated December 13, 198 The NRC inspectors also were given a presentation describing the licensee's E0 program on November 18, 1985, during which requirements and procedures in the above documents were discusse The licensee's program was reviewed to verify that adequate procedures and controls had been established to meet the recuirements of 10 CFR 50.49. Areas of the program reviewed included methods and their effectiveness for:

- Requiring all equipment that is located in harsh environments and is within the scope of 10 CFR 50.49 to be included on the list of equipment requiring qualification (EQ Master List).

- Controlling the generation, maintenance, and distribution of the EQ Master Lis Defining and differentiating between mild and harsh environment Establishing harsh environmental conditions at the location of equipment through engineering analysis and evaluation.

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- Establishing and maintaining a file of plant condition Establishing, evaluating, and maintaining E0 documentatic Training p0rsonnel in the environmental qualification of equipmen Controlling plant modifications such as installation of new and replacement equipment, and providing for updating replacement equipment to 10 CFR 50.49 criteria.

Procedure NE0 2.21 establishes the EQ program for all Northeast Utilities nuclear plants including Millstone 1 and 2. The major lower tier implementing procedures are GE-EQ-01 which provides instructions for generating and maintaining the Master List and

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i documentation files, and ACP-QA-2.16 which covers installation,

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maintenance, and repair of EQ equipmen The NRC inspectors concluded that the Cesign Control requirements of Criterion III of Appendix B to 10 CFR 50 were not properly irplemented in one respect. The existence of numerous' unsigned and undated markups and corrections on System Component Evaluation Worksheets (SCEW sheets) critical to documenting component qualification demonstrated improper control of revisions to the EQ documentatio The inspectors recognized that these markups constituted only a temporary step in the generation of clean unmarked SCEW sheets, and that the marked SCEW sheets would not be used by personnel other than the group performing the markups; nonetheless, the ability of that very group to review its own work was significantly degraded by the anonymous changes. Minutes of an October 31, 1985 meeting document the licensee's intention to control EQ documents, and the licensee described and began implementation of acceptable control measures prior to the end of the inspection. Documentation deficiencies constitute Potential Enforcement / Unresolved Item 50-245/85-30-2; 50-336/85-35- Procedure NE0 6.02 is an existing procedure that was revised to include procurement of EQ equipment. Procedure review and personnel interviews by the inspectors identified one deficiency in an otherwise acceptable EQ procurement process. Although procedure GE-EQ-01 correctly identifies that EQ documentation reviews must apply current qualification criteria (specified as MUREG-0588 Category I) to replace-ment equipment purchased after February 22, 1983, this provision is not clearly stated for procurement purposes and is not specified in NE0 6.02. A future NRC inspection will verify that the procurement procedures clearly require current qualification criteria. Replacement equipment procurement constitutes Open Item 50-245/85-30-4; 50-336/

85-35- Section V. A of the Attachment 8.A to NE0 2.21 applies the Northeast Utilities Quality Assure.nce Program to the EQ program. The inspectors interviewed Corporate QA personnel concerning their involvement in the EQ program. A QA surveillance of the EQ files was conducted from October 30 through November 1, 1984. The results were documented in Surveillance Report No. CB-1136, dated November 2, 1984 Eleven findings were identified in this surveillance. Resolutions to these findings were documented in a memo (GLJ-84-244) from G.L. Johnson to F.C. Libby dated November 30, 1984. A followup surveillance on these findings was conducted on June 12, 1985, and the results were documented in Surveillance Report No. CB-1136 Some of the identified findings were still not resolved due to the fact that the EQ files were still being update Licensee QA will continue followup on these item The inspectors also interviewed plant site QA personnel concerning their involvement in the EQ program. The site QA team consists of three groups. The Monitoring Group performs QA monitors (audits) in

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various functional areas, including EQ related activities. At least twelve monitors are to be performed each year on each plant. The Procurement Group conducts receipt inspections on newly purchased items against procurement specification requirements (including EQ replacement items). The Inspection Group provides QC inspectors to inspect completed activities which require QC inspections. Tha same QA team covered all three plant Section V.B of Attachment 8.A to NE0 2.21 specifies EQ-related training requirements. The inspectors interviewed personnel and reviewed records covering EQ training of both headquarters and plant personne Applicable training given to headquarters personnel is as follows:

- IEEE Standard 383 (1974) and R.G.I.131 - Type test of Class 1E electric cable, field splices, and connectors for nuclear power generating station (NPGS) held on October 19, 1983, attended by fifteen student IEEE Standard 382 (1980) and R.G. 1.73 - Type test of Class 1E electric valve operators for NPGS, held October 5,1983, attended by fifteen student IEEE Standard 334 and R.G.1.40 - Type test of continuous duty Class 1E motors for NPGS, held September 21, 1983, attended by twenty-four student IEEE Standard 323 and R.G. 1.89 - Qualifying Class IE eouipment for NPGS, held on September 7, 1983, attended by fourteen student IEEE Standard 317 and R.G. 1.63 - Electrical penetration assemblies in containment structure, held September 2, 1983, attended by fourteen student A one-day general EQ training session was presented at the site by a contractor four times in May and June,1985; fifty personnel attended, covering engineering, QA/QC, and other areas including maintenance personnel at the level of assistant supervisor (foreman) and abov All site personnel receive two nours general EQ instruction during rotating annual training (for which attendance records are kept).

All personnel also receive departmental training on procedures that are prepared to implement ACP-QA-2,16 and on other subjects. The training department is also developing a program intended for INP0 accreditation, which will include maintenance of EQ equipment.

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It is concluded, with the exception of the two items described above, that the EQ program is well planned and documented, and has been properly implemented as required by 10 CFR 50.49, i

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B. E0 Maintenance Program Implementation of the EQ maintenance program wi.s inspected to assess the licensee's capability for preserving the qualified status of electrical equipment defined by 10 CFR 50.4 Section IV of i

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i Attachment 8.A to NE0 2.21 defines the licensee's program for preserving the cualified status of equipment through specific main-tenance activities. Procedure ACP-QA-2.1.6 is the lower tier controlling document for installation, maintenance, and repair of equipment that is required to be environmentally qualified in all three Millstone units. Page 4 of each SCEW sheet defines the EQ-

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related maintenance and surveillance activities required for each type of componen At the time of the inspection, all the SCEW sheets defining EQ main-tenance requirements were completed, but mot all of them had been received and reviewed by maintenance personnel and not all of the implementing maintenance procedure preparation and modification were complete None of the Unit 1 procedures were completed, while several of the Unit 2 procedures were issued. In the interim, ACP-QA-2.16 provides for control of EQ-related maintenance by Generation Electrical Special Programs and Studies, the headquarters EQ engineer ACP-QA-2.16 covers identification and performance of maintenance required to preserve qualification; definition of procedures; and concern for impact of plant modification on EQ components. All EQ engineers carry beepers to ensure their availability at all time The licensea stated that plant review of all SCEW sheets will be completed by February 1986, and that all EQ-related maintenance procedures for Units 1 and 2 will be issued by August 31, 1986. A future NRC inspection will review the completion of these activitie Completion of maintenance program constitutes Open Item 50-245/85-30-5; 50-336/85-35- While reviewing the licensee's EQ maintenance program the inspectors reviewed the following additional documents and records:

- Unit 2 Station Procedure MP 2720T, Maintenance of Unit 2 EEQ Equipment, Rev. O, February 1,1985 - covers electrical equipment

- Unit 2 Station Procedure IC 2418M, EEQ Qualification and Maintenance Program, Rev. O, February 1, 1985 - covers instrumentation

- Departmental Instruction 2-MPM-1.43 Rev. O, dated October 29, 1985 -

states that any component bearing green EEQ sticker requires consulting Maintenance Engineer prior to starting any work

- Unit 1 Station Procedure Spec. Proc. 82-1-34, Installation of Conax Connectors for MSIV Limit Switches, Rev. O, November 2, 1982 (with Change Nos. 1, 2, and 3)

- Unit 1 Station Procedure MP 760.2, Maintenance and Repair of ASCO Solenoid Valve Model 206-832, Rev. 0, September 24, 1985 (with Change No. 1)

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- Unit 1 Station Procedure MP 760.3, Rebuild / Repair of ASCO Series NP8316 Solenoid Valves with 5/8" Orifice, Rev. O, October 16, 1985

- Unit 2 Station Procedure IC 2417N, RCS RTD Installation Procedure, Rev. 1, July 5, 1984

- Unit 2 Station Procedure IC 2417P, Installation and Maintenance of Conax Electrical Seal Assemblies, Rev. O, April 4,1985

- Unit 2 Station Procedure IC 2418J, Foxboro N-Ell and N-E13 Series XMTRS - Installation / Calibration / Servicing, Rev. 3, November 7, 1983 (with Change No. 1)

- Unit 2 Station Procedure IC 2418K, Installation / Calibration and Servicing of Rosemount Model 1153 Series Pressure Transmitters, Rev. O, November 7,1983

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- Unit 2 Station Procedure IC 2418N, Maintenance / Installation /

Calibration of Static-0-Ring Pressure Switches, Rev. O, June 18,

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- PMMS Maintenance Record Printouts for calibration and 0-ring replacement for transmitters covered by IC 2418J and for HPCI pump motors NNEC0 has developed a computer based Production Maintenance Management System (PMMS) to aid in controlling maintenanc EQ

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requirements are being integrated into the PMMS, which includes the l

following subsystems:

- Equipment Identification, including capability to provide automated listings

- Work Orders, including capability to create, change, olan, schedule, and track, and to generate repetitive work orders

- History, including not only completed work order storage but also statistical and trending analysis capability

- Material Support, using Purchasing, Stores, and Accounts Payable data

- Planning Support

- Scheduling Support

- Interface (to such external systems as Health Physics and NPRDS)

No deficiencies were identified as a result of our review of the above documents and record E0 Master List The licensee is required to maint.in an up-to-date list of the equipment that must be qualified under 10 CFR 50.4 Separate Master

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Lists for Units 1 and 2 are maintained by Generation Electrical Special Programs and Studies. Considered in the preparation and maintenance of these lists are the environmental effects resulting from all of the postulated design basis accidents documented in the Updated Safety Analysis Reports, Technical Specification limiting conditions of operation, emergency operating procedures, Material Equipment and Parts Lists, piping and instrumentation diagrams (P& ids),

and Plant Design Change Requests (PDCRs).

The methodology used for producing the EQ Master Lists is described in licensee submittals dated February 11, 1985 for Unit 1 and December 18, 1984 for Unit 2. The Master Lists are maintained under Procedures NE0 2.21, GE-EQ-01, and NE0 3.03; the latter covers review of all PDCRs for EQ impact. These procedures were reviewed and found acceptable for maintaining the Units 1 and 2 Master List In order to test the completeness of the licensee's Master Lists, five components or groups of components were selected for each Unit from the following Emergency Operating Procedures:

Unit 1:

- OP 502B Rev. O, April 14, 1979, Emergency Plant Shutdown

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- OP 506A Rev. 0, January 1, 1980, Loss of Coolant

- OP 516A Rev. 3, January 1,1980, Emergency Shutdcwn Af ter a Condensate or Feedwater Line Rupture (Loss of Feedwater)

- OP 516B Rev. 1, September 27, 1978, Nuclear Steam System Rupture Unit 2:

- E0P 2525, Rev. O, January 1,1984, Standard Post Trip Actions

- E0P 2532 Rev. 1, July 26, 1984, Loss of Primary Coolant

- E0P 2536 Rev. O, January 7, 1984, Excess Steam Demand The procedures listed for Unit 1 have been superseded by new symptom-oriented procedures and were used for the inspector's convenience; for each sample selected the applicability to current procedures was verified, lhe licensee was able to either show that the selected equipment was on the Master List or justify its exclusion, using applicable P& ids, Master Lists, and the EEQ Environment Fil .

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D. Environmental Qualification Files The EQ files for Millstone Units 1 and 2 are each divided into two parts, covering environment and equipment. The EEQ environments file for each unit, known as the "100" file, describes and tabulates the normal and accident environmental conditions in plant areas where electrical equipment is located, and provides the references from which the environmental parameters were obtaine a

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The EE0 equipment files are arranged by manufacturer, and contain the documents that establish environmental cualification for component types. They include the following:

- Cover sheet, with signoffs

- Action items requiring closecut

- Applicability of references to each specific component

- Summary evaluation with component description, level of qualification, limitations (such as conditions on installation or maintenance), and discussion of points requiring elaboration

- Four page System Component Evaluation Worksheets (SCEW sheets),

arranged as follows:

p.1 - summary of qualification requirements p.2 - notes and references p.3 - materials and analysis data p.4 - maintenance and surveillance requirements

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EQ assessment checklist

- References such as test reports, IEB and IN responses, calculations, and memos The NRC inspectors examined files for twelve equipment items in Unit 1 and eight items in Unit 2, where an item is defined as a specific-type of electrical equipment, designated by manufacturer and nodel, which is representative of all identical equipment in a plant area exposed to the same environmental service conditions. The items were selected in advance by the inspection team and identified to the licensee during the entrance meetin The files were examined to verify the qualified status of equipment within the scope of 10 CFR 50.49. In addition to comparing plant service conditions with qualification test conditions and verifying the bases for these conditions, the inspectors selectively reviewed areas such as required post-accident operating time compared to the duration of time the equipment has been demonstrated to be qualified; similarity of tested equipment to that installed in the plant (e.g.,

insulation class, materials of components of the equipment, tested configuration compared to installed configuration, and documentation of both); evaluation of adequacy of test conditions; aging calculations for qualified life and replacement interval determination; effects of decreases in insulation resistance on equipment performance; adequacy of demonstrated accuracy; evaluation of test anomalies; and applicability of EQ problems reported in IE ins /Eulletins and their resolutio o

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The files adequately documented qualification of the equipment except as described below. The files were readily auditable and with the exceptions described below were complete and accurate. No generic documentation deficiencies were foun (1) Limitorque operators, EEQ File No. MP1-122 - The NRC inspectors observed two types of internal wire in Limitorque operators that were not fully qualifie First, because of high ambient temperature at the location of operator MS-5, internal Brand Pex wiring does not have the 40 year qualified life claimed in the file. Second, qualification was not documented for "Thermofit CSA 125*C HSCF 100" wire as observed in operator LP-10A during the walkdow The possibility of additional unqualified internal wiring could not be ruled out during the inspectio (1) Review of maintenance records for operator MS-5 showed that the licensee had not completed inspection of all qualified Limitorque operators to address the concerns -- including wiring -- of IE IN 83-7 (2) Procedures used for installation of wiring by the licensee had not controlled the type of wire to permit tracin (3) Wiring installed by Limitorque and possibly by others (such as valve manufacturers) had not been ad @esse When advised of these concerns, NNECO coninitted to taking positive actio Every type of wiring used in Millstone Unit I and 2 Limitorque operators will be evaluated, using walkdown inspections and records to identify the wiring types. Any wire that cannot be identified will be replaced with wire shown to be qualified for the application. Any wire for which the qualified life is determined to be less than 40 years will be replaced before the end of its actual life. Limitorque operator wiring constitutes Potential Enforcement / Unresolved Item 50-245/85-30-1; 50-336/85-35- An internal licensee memo dated November 8, 1985 states that operator LP-10A was suspected of having a Curtis type CDM terminal block, which would require replacement. The NRC walkdown inspection verified the presence of a Curtis block, of indeterminate model number. This concern is unresolved pending NRC review of the licensee's determination concerning terminal block qualification, and possible corrective action. Limitorque terminal block constitutes Potential Enforcement / Unresolved Item 50-245/85-30- (2) Solenoid valve wiring \ IE Information Notice (IN) 84-68 identifies a jossible problem with field installed wiring being exposed to excessively high temperatures inside solenoid valves subject to self heating effect Internal licensee memos dated February 7 and September 17, 1985 call out eighteen solenoid valves with 4'eficiencies in improperly rated field wiring in Unit 1, in the Post Accident Sampling System and H 0 Monitoring System. Ten of the valves are Valcor a$d hight are Target Rock. They are as follows:

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Valcor Target Rock 1-AC-194 1-AC-199 1-PAS-1 1-PAS-24 1-AC-195 1-AC-202 1-PAS-5 1-PAS-25 1-AC-196 1-AC-203 1-PAS-17 1-PAS-35

. 1-AC-197 1-AC-205 1-PAS-20 1-PAS-42 1-AC-198 1-AC-206 The September 17 memo also cites procurement problems such as vendor qualifications and insulation suitability as the reason that suitable replacement cable had not been obtained as of that date, even though it was ordered on March 22. Although these valves are all R.G.1.97 equipment not yet included in the EQ Master List at the time of the inspection, a future NRC inspection will verify that corrective action is complete Solenoid valve wiring constitutes Open Item 50-245/85-30- (3) ASCO solenoid valve conduit for Unit i valves 1-MS-1A, B, C, D -

Page 4 of the SCEW sheet (dated November 15,1985) states that at the next normal maintenance interval, a one quarter inch weep hole should be drilled at the conduit system low point nearest the 50V housing. The licensee explained and the inspectors agreed that the existing installation with junction box drain holes is adequate to support qualification based on ASCO test report AQR-67368 Rev. 1; the new weep holes will be engineering improve-ments not required to support qualification. A future NRC inspection will verify that the weep holes are drilled. Conduit weep holes constitute Open Item 50-245/85-30- (4) Motor maintenance requirements - Files were reviewed for two types of motors, Unit 1 LPCI pumps M8-75A, 3, C and Unit 2 HPSI pumps P-41A, B, and In each case page 4 of the SCEW sheet referenced the manufacturer's instructions (and for the Unit 1 motors, the General Electric Topical Report). The references do not adaress specific portions of the manufacturer's recommendations to clearly define the minimum maintenance required to preserve qualification. Maintenance records showed that only a portion of the total maintenance operations described in the references were actually being performed. Considering the nature of the omitted operations (including various duty cycles, design variations, and abnormal operations such as drying insulation) and the relatively short time that the motors have been operated, it was determined that this maintenance issue would not affect the current qualified status of the motor A future NRC inspection will verify that licensee corrective action clearly identifies EQ-related motor maintenance and surveillance requirements in the EQ files and maintenance procedures. Motor maintenance requirements constitute Open Item 50-245/85-30-8; 50-336/85-35- (5) IE ins and Bulletins - The NRC inspectors reviewed and evaluated the licensee's activities related to the review of EQ-related IE Information Notices and Bulletins. The inspectors'

review included examination of procedures and EQ documentation packages relative to Information Notices and Bulletin The

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a procedures reviewed determined that the licensee does have a system for distributing, reviewing, and evaluating ins / Bulletins relative to equipment within the scope of 10 CFR 50.49, and that ins and Bulletins are addressed in appropriate com]onent EQ files as described above. During the review of individual component qualification files the NRC inspectors evaluated the licensee's actions with respect to ins and Bulletins. No concerns were identified during this review except as described in section 4.D(1) 84-68 with respect to IE IN 83-72 and 4.D(2)

for IN 84-6 E. PLANT PHYSICAL INSPECTION The NRC inspectors, with component accessibility input from licensee personnel, established a list of nine components types in Unit 1 and four in Unit 2 for physical inspection. All were accessible at the time of inspection, including equipment inside the drywell of Unit I which was shutdown. The inspectors examined characteristics such as mounting configuration, orientation, interfaces, model number, ambient environment, and physical condition. Concerns noted during the walkdown inspection are addressed in section D of this report. No evidence was fount of generic or widespread deficiencies in the installation or maintenance of EQ equipmen ,

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