IR 05000423/1985034

Insp Rept 50-423/85-34 on 850708-12.No Violations Identified.Major Areas Inspected:Activities Re Installation of safety-related Electrical/Instrumentation Components & Associated Circuits

ML20135A442
Person / Time
Site:	Millstone
Issue date:	08/29/1985
From:	Anderson C, Paolino R, Phelan P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20135A423	List: IR 05000423/1985034 ML20135A420
References
50-423-85-34, NUDOCS 8509100161
Download: ML20135A442 (9)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-423/85-34 Docket No. 50-423 License No. CPPR-113 Priority -

Category B Licensee: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Energy Station, Unit 3 Inspection At: Waterford, Connecticut Inspection Conducted: July 8-12, 1985 Inspectors: .,'

l P. H. Phelan_ eactorhngineer

, date f'79_86_

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' .PW Lead Reactor ;ngineer date Approved by: _

. Ariderson, Chief 1 29/P[

date Plant Systems Section, DRS In_spection Summary: Inspection on July 8-12,1985(InspectionNo. 50-423/85-24)

Areas Inspected: Routine, unannounced inspection of activities relating to the insta1TitTon of safety-related electrical / instrumentation components and associated circuits, quality control docurentation and licensee action on previous inspection findings. The inspection involved 68 inspection hours on site by two region based inspector Results: No violations were identifie $

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l DETAILS 1.0 Persons Contacted 1.1 Northeast Utilities Service Company (NUSCo)

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B. Olsen, I&C Engineer B. Lepper, Electrical Engineer 1.2 Northeast Nuclear Energy Company (NNECo)

• J. O. Grockett, Superintendent

• K. W. Gray, Jr. , Staff Assistant

• L. J. Nadeau, Assistant Project Engineer

• J. S. Nicosia, EEQ Engineer R. Fraser, Assistant I&C Supervisor

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M. Brown, I&C Supervisor l B. Enguch, Assistant Supervisor l J. Goodier, Instrumentation Specialist j L. Chiartzia, I&C Engineer J. Chiloyan, Project Engineer

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l 1.3 Stone & Webster Engineering _ Corporation (S&W)

• G. J. Basilesco, Engineer

• J. A. Capozzoli, Supervisor of Construction Services

• C. A. Kuhns, Assistant QA Program Administrator I * M. R. Mathews, Assistant Superintendent-FQC l * P. A. Nelson, Lead Electrical Engineer i * W. Von, Senior FQC Engineer l B. Smith, I&C Engineer N. Piccolo, Sr. Electrical Designer D. Dakers, Structural Engineer B. Martin, Electrical Engineer 1.4 Westinghouse M. Brothers, Process Control Engineer 1.5 U.S.NuclearRegulatoryCommission(USNRC}

• T. Rebelowski, Sr. Resident

! * denotes personnel present at exit interview.

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2.0 Facility Tour

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- The inspectors observed work activities in progress, completed work and plant status in several areas of the plant during a general

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j inspection of the site. The inspectors examined work items for obvious defects or noncompliance with NRC requirements or licensee

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commitments. Particular note was taken regarding the presence of quality control personnel and indications of quality control l activities through visual evidence such as inspection records, I nonconformance and acceptance tags.

l Specific work activities of completed work observed by the inspectors

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included installation of instruments, routing of instrument cables and instrument tubing, and installation of cable trays and condui .2 During the facility tour and in the company of licensee representa-tives, the inspector noted that the effluent sample Ifnes used to extract a representative air sample for the Effluent Radiation Monitors Nos. 3 CMS *RE22A&B and 3HVR*RE19A&B in the Auxiliary Build-ing, elevation 71' 0" consisted of 3/4" stainless steel tubing with several 90 degree fittings at the point of entry to the effluent l Radiation Monitor sample chambe Specification M-624, page 1-35, l line 30.34 states in part, that: "All piping, tubing, valves and fittings must comply with ---- Specification No. 2472.800-943, Stone and Webster Instrumentation Installation - ." Specification No. 2472.800-943, page 281-7, line 5.20 states, in part, that: "All tubing installations connecting radiation monitors"containing gaseous samples to their sample source and return points shall contain tube l bends with a minimum bend radius of nine tube diameters". Construc-l tion drawings Nos. EK-515006 and EK-515003 approved for construction l on December 20, 1984 call for the use of 90 degree Parker-Hannifin

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fittings instead of the nine tube diameter radius specified in Specification No. 2472.800-943. Quality Control Inspection Report (QCIR) No. SA00631 accepts the Radiation Monitor 3HVR*RE19A&B

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installation based on compliance with the construction drawing l EK-515003. This item is unresolved pending determination of the

! applicability of the 2472.800-943 specification for tube bend

) minimum bend radius of nine tube diameters to the 90 degree l Parker-Hannifin fittings (423/85-34-01).

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3.0 Licensee Action on Previously Identified Items

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3.1 (Closed) Unresolved Item No. 84-23-02 pertaining to the over fill of cable tray 3TC401P.

l The inspector reviewed NETM, Rev. 1, Structural Design Criteria for '

Category I Cable Tray Supports. The procedure requires that each l cable tray be analyzed with respect to cable loading prior to an after building turnover. Cable trays are required to be kept below '

l 50% full to provide adequate assurance that the actual weight of the l cables and the tray does not exceed the design basis of their support In respect to tray 3TC401P where thc actual weight, 42.63

, #/ft, exceeded the design basis, 42.50 #/ft, an analysis shall be l performed to determine if the supports are adequate. In addition, one month prior to scheduled building turnover an Electrical Physical Designer (EPD) will notify the Cable Tray Verification

, Coordinator (CTVC) of any cable being added or changed. At this j time any trays which are found to be ever loaded will be provided j with additional supports or modifications. This item is closed.

l 3.2 (Closed) Unresolved Item No. 84-23-04 pertaining to intercell connections on the safety related batteriss without the manufacturers recommended insulating materia The inspector reviewed Engineering & Design Coordination Report (E&DCR) No. T-E-05027 to assess the licensee's corrective action to

! resolve this issue. Inserting the cable insulation within the lug shank and crimping the lug connection stiffens the connection and protects the wire from the corrosive effects of the battery room l atmosphere. E&DCR No. T-E-05027 calls for the installation of type l WCSF-100N Raychem Heat Shrink Tubing Cover on all affected battery l intercell cable connection This item is closed.

l 3.3 (0 pen) Unresolved Item No. 84-23-01 pertaining to the violation for

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l failure to follow procedure The inspector was provided a copy of the letter sent to the NRC in i Region I, dated April 19, 1985, concerning the violation in

! Inspection Report No. 50-423/84-23. The letter contained a condition, response and corrective and preventive action associated with the two examples which rade up the one violation.

l The response to the black cable entering electrical penetration No. F3V, which was not appropriately color coded, was found to be

! adequat The licensee inspected all penetrations for similar

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examples, but found no further problem This was an isolated case and no further corrective action is require .

e m _A____ ___m_m_____m _-___.____ . _ - _ _ _ ___________

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The response to unsupported cables coming from cable tray 3TC0010 to cable trays 3TC0020 and 3TC0080 was not adequately addressed. The response addressed cables that were unsupported in the vertical position, where as, the violation was for cables unsupported in the horizontal positio Further information is required from the licensee before this item can be fully closed. This item remains ope .0 Instrumentation (Components / Systems) Work Observation r The inspector observed work performance, completed work and partially completed work of activities relating to the installation of instrumentation and controls associated with pressure, level, flow and radiation monitoring to ascertain whether the installation was performed in accordance with applicable procedures, FSAR and licensee commitment '

4.1 Items examined for this determination include:

• Pressurizer level transmitter No. 3RCS*LT461, located in the Containment Building,

• Pressurizer pressure transmitter No. 3RCS*PT471, located in the Containment Building

• Accumulator level transmitter No. 3SIL-LT954, located in the

Containment Building, elevation-2',

• Accumulator pressure transmitter No. 3SIL-PT965, located in the Containment Building, elevation-2',

• Compont Cooling Flow Transmitter No. 3CCP-FT1788, located in the Containment Building, elevation 4'-6",

• Process Radiation Monitor No. HVR11-1.2 located in Auxiliary Building, elevation 66'-6",

• Steam Generator Level transmitter No. 3FWS*L1529A, located on the Auxiliary Shutdown Panel,

• RCS Pressure Transmitter No. 3RC5*P1405B located on Auxiliary Shutdown Panel,

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• Drawing No. 2472.710-292-545, Rev. 2, Feedwater System Steam

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' ,. * Drawing No. 12179-EK-501099, Containment Structure,

• Drawing No. 12179-LP-382717, Safety injection level transmitter

' piping,

' Drawing No.12179-FSK-6-18, Flow Diagram Feedwater, and

• Drawing No. 12179-EK-501162, Containment Structur <-

4.2 No violations were identifie f f

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5.0 Instrumentation (Component / System) --- QA Record Review The inspector reviewed pertinent work and quality records for safety related instrumentation and control installations to ascertain whether the records meet established procedures and whether the records reflect work accomplished consistent with NRC requirements and licensee commitments in the area of receipt inspection, procurement, installation and quality control inspection .1 Items examined for this determination include:

• Spec. No. 2472.800-943, Instrumentation, Installation, Piping &

Tubing, Rev. 10, Feb. 12, 1985,

• Spec. No. 2472.110-611, Instr.' Valves & Manifold Valve Assembly, Rev. 2, Jan. 28, 1933,

• J.0, No. 12179, Technical Requirements for. Manifold Valve Assemblies, June 9, 1978,

• Purchase Spec. No. 2472.510-662, Electronic Pressure and Differential Pressure Transmitters.-Cat. I., July 2, 1982,

• Purchase Order No. 2472.510.662. Electronic Pressure and-Differential Pressure Transmitters, March 23, 1982,

• Nonconformance/ Deviation Report No. 8898 July 24, 1984,

• Certification of Compliance for LT461 and PT 965, November 9, 1982,

• Quality Assurance Report No. M31066200C1, September 23, 1982,

• Product Quality Certification, P.O. No. 2472.510-662, September 23, 1982,

• Certification of Compliance P. O. No. 388007, September 22, 1982,

• S&W QAIR No. ISA00875, May 31,.1985,

• S&W E&DCR No. P-T-5631, April 27,1983,

• S&W Material Receiving Report, P. O. No. 2400.000.001, April 12, 1985,

• Westinghouse Quality Release, P. O. No. 2400.000-001, March 26, 1985,

• S&W QAIR No. ESA51583, April 20, 1985,

• Westinghouse,' Change Notice Order No. HR-30927 AR6/N, August 25, 1975,

• Specification No. M-624, addendum 3, dated June 21, 1984, for all Radiation Monitors including the Containment High-Range Monitor, Particulate / Gas Monitor, In-Line Liquid / Gas Monitor and Area Monitors,

• Containment High-Range Monitor Qualification Report No. 51654-1 (Wyle) dated May 18, 1984,

• Containment High-Range Monitor MI cable Qualification test critique (Kraman) dated December 1984,

• Meeting Notes of Conference, M. Kaman Company office, held on July 10-11, 1984, to discuss methodology of Kamman's Qualification Program and status of qualification effort. (Ltr. No. NES-36057),

• Qualification of Model KDI-1000 High Range Containment Area Radiation Detector and Mineral Insulated (MI) cable system, Report No. 460036-001 Revision A, and

• Generic Qualification Test Report Action Lab Report No. 16683- ,

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5.2 In reviewing the above documents the inspector noted that:

(a) The Activation Energy constant (ev) of the limiting material (Silicon Rubber) used in determining the qualified life for the Kaman detector assembly differs between test labs. Wy le Report No. 57654 page 7 (revision A) uses an activation Energy of 1.86 ev for Silicon Rubber and Acton Report No. 16683-1 page 8-5 uses an Activation Energy of 0.91 ev for Silicon Rubber. Though the qualified life in either case is in excess of 40 years, the inspector requested clarification on the use of different activation Energy constant for the same limiting material (Silicon Rubber). This item is unresolved pending NRC review of license evaluation. (423/85-34-02)

(b) The Kaman mineral-insulated (MI) cable assembly is not qualified for the LOCA environment. Acton Environmental Testing Corporation Report NO. 16683-1 page 10-10 contains notations which state that: " Based on the above results the item described in Section 4-0 has satisfied the requirements with the exception of operability during the LOCA test -- .

However, due to a failure of the coax mineral insulated cables inside the test chamber during the LOCA Test, operability of the ion chamber was not demonstrated during the LOCA event."

Notes from a conference held in the Kaman Company office on July 10-11,1984 (Ltr. No. NES-36057) indicate problems in qualifying MI cable assembly. Discussions included material design problems which resulted in failure of 1983 Qualification type tests. Kaman MI cable Qualification Test Critique dated December 11, 1984, discussed additional failures and methods for a connector to achieve hermetic seal. However, none of the methods discussed have been tested in the LOCA environmen The Qualification Report No. 460u36-001 Revision A referenced in the MI cable Qualification Critique describes in detail the Qualification Plan, however, it contains no test data or test results to indicate MI cable assembly is qualified in a LOCA environment.' This item is unresolved pending NRC review of qualifying test data for the MI Cable / Connector assembl (423/85-34-03)

(c) Sensitivity data for the effluent monitors was not available for review. Regulatory Guide 1.21 Item C.3 requires that effluent monitors demonstrate compliance with Technical Specification and/or 10 CFR Part 20, Appendix B effluent limit Discussions with the licensee indicate this information was not supplied by the manufacturer of the effluent Radiation Monitor This item is unresolved pending NRC~ review of equipment sensitivity data for effluent Radiation Monitor which demonstrate compliance with 10 CFR Part 20, Appendix B effluent limit (423/85-34-04)

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6.0 Instrumentation (Cables / Terminations) --- Work Observation The inspector observed work performance, partially completed work and completed work pertaining to the installation of instrument cable and termination to determine whether the requirements of applicable specifications, instructions and procedures are being met in areas relating to material qualification, type, size, routing termination and separation. ,

6.1 Items examined for this determination include:

• Instrument cable 3CCPBPX278 routing and termination from transmitter 3CCP*PT1788 to instrument panel 3CES*IPNL119

• Instrument cable 3RMSN0X-408 routing and termination from detector 3HVR*RE10A1 to micro-computer cabinet 3HVR*RIY10A

• Instrument cable 3FWSA0X205 routing and termination from transmitter 3FWS*LT529A to instrument panel 3CES*IPNLI22

• Instrument Loop Calibration Report (ILCR) No. 3HCR-010A, Rev. 1 April 30, 1985

• ILCR No. 3FWS-529A, Rev. 2, April 18, 1985

• ILCR No. 3CCP-1788, Rev. 2, Jan. 19, 1985

. * Spec No. 2400.000-350, Electrical Installation, Rev. 8 May 30, 1985

• S&W Cable Pull Ticket (CPT) for cable 3FWSA0X205 dated Oct.10, i98 *S&W Conductor Termination Sheet (CTS) for cable 3FWSA0X20 *S&W CPT, for cable 3RMSN0X021 dated March 13, 1985

• S&W CTS, for cable 3CCPBX277 dated Jan. 29, 1985 ,

• S&W CTS, for cable 3CCPBX277 dated April 17, 198 .2 No violations were identifie .0 Instrumentation (Cables & Terminations) --- QA Record Review The inspector reviewed pertinent work and quality records relative to safety related instrument cables, including terminations and associated hardware, to ascertain whether the records meet established procedures and whether the records reflect completed work consistent with NRC require-ments and licensee-commitments in the area of receipt inspection, material certification, and installation and quality control inspectio .1 -Items examined for this determination include:

• S&W QAIR No. E4A65485,-July 28,'1984, Cable Installation-General

• S&W QAIR No. E4A6661, Sept. 8, 1984, Cable Terminations and

. Connections-General

• S&W E&DCR No..F-E-43360, July 10, 1985-

• Cable-No. 3CCPBPX277 pull ticket dated Sept. 9, 1984

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• Cable No. 3RMSN0X021 pull ticket dated March 13, 1985

• Cable ~ No. 3FWSA0X205 pull ticket dated Oct. 10, 1984 7.2 No violations were identifie '

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,8. 0 Unresolved Items 8.1 Unresolved items are matters about which more information is needed to determine whether it is acceptable or a violation. Unresolved items are discussed in paragraphs 5.2(a), 5.2(b) and 5.2(c).

9.0 Exit Meeting The inspector met with the licensee and construction representatives at-the conclusion of.the inspection on July 12, 1985, at the construction site. The inspector summarized the-findings or the inspection and the licensee acknowledged the inspectors comment The licensee was informed that the paragraph on proprietary information would no longer appear in the cover. letter and that the manual chapter places responsibility upon the licensee to inform the inspectors that material provided during this inspection is proprietary and is to be omitted from-the report. There was non At no-time'during the inspection was written material provided to the licensee by the inspecto ~