IR 05000353/1986009

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Insp Rept 50-353/86-09 on 860512-16.No Violation Noted. Major Areas Inspected:Ae & Contractor Activities Re safety- Related Electrical Sys,Procedures,Records & Workmanship
ML20206M357
Person / Time
Site: Limerick Constellation icon.png
Issue date: 06/18/1986
From: Anderson C, Paulitz F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20206M338 List:
References
50-353-86-09, 50-353-86-9, NUDOCS 8607010159
Download: ML20206M357 (10)


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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No.

50-353/86-09 Docket No.

50-353 License No.

CPPR-107 Category A

Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, PA 19101

Facility Name:

Limerick Nuclear Generating Station, Unit 2 Inspection At:

Lijerick, Pennsylvania

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Inspection Conducted: May 12-16, 1986 Inspectors:

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d-98d F. Paulitz, Reactor Engine)r date Approved by:

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C. f/. Anderson, Chief, Plant Systems

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Section, EB, DRS

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Inspection Summary:

Inspection Report No. 50-353/86-09 on May 12-16, 1986 Areas Inspected:

Routine, unannounced inspection by one regional based inspector of licensee, architect engineer and contractor activities relating to safety-related electrical systems, procedures, records and workmanship.

Results: No violations were identified.

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DETAILS 1.0 Persons Contacted 1.1 Philadelphia Electric Company

  • P. Naugle, Assistant Construction Superintendent G. Lauderback,Jr., Field Quality Assurance Branch Head
  • K. Meck, Quality Assurance Engineer, Long Term Maintenance
  • T. Dey, Quality Assurance Engineer
  • T. Tucker, Quality Assurance Engineer
  • D. Paolo, Quality Assurance Engineer 1.2 Bechtel Construction Incorporated
  • G. Bell, Project Quality Assurance Engineer
  • R. Lanemann, Project Field Supervisor
  • V. Mehta, Lead Mechanical Engineer
  • K. Swartz, Project Quality Assurance Engineer
  • D. Roof, Lead Valve Engineer
  • G. Kelly, Quality Assurance Engineer
  • K. Wolff, Quality Assurance Engineer
  • M. Drucker, LRE-Quality Assurance Engineer
  • R. Palanitwamy, Assistant Project Engineer
  • K. Quinter, Quality Control Engineer
  • denotes those present during the exit interview.

2.0 Procedure Review The licensee documents associated with the procurement, storage, instal-lation and inspection of the class 1E electric systems were reviewed by the inspector.

This review was to determine whether the technical requirements of the licensee safety analysis report (SAR) and NRC requirements had been adequately translated into applicable documents.

The review was also to determine if the construction specifications, drawings, work procedures and instructions were of sufficient detail and clarity for adequate work performance and control.

The specific documents reviewed during this inspection of the Class 1E electric systems are listed in attachment A. _

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The documents that were reviewed provided adequate control of procurement, storage, installation and inspection of Class 1E electric systems to assure that these systems and qomponents meet all engineering function requirements. These function requirements include performance, maintain-ability, fit and safety requirements that meet the licensee SAR commit-tments and NRC requirements.

3.0 Record Review A selective sample of licensee records, associated with the Class IE electric systems, were reviewed by the inspector.

This review was to ascertain effectiveness of the licensee quality assurance program in the area of procurement, storage, installation and inspection of the class IE electric systems to assure that the systems j

and components perform their safety-related functions.

The licensee has a system for preparing, reviewing and maintaining records

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which is in accordance with the SAR committments and NRC requirements. See attachment A for records reviewed.

The listing of the licensee QA audits and the specific audits reviewed indicates that there were two type of audits.These audits are by :

direct inspection of electrical activities personnel performance of various inspections and maintenance activi-ties associated with electrical components.

Nonconformance reports (NCR) reviewed were written legibly,and correctly described the deficiency. The NCR disposition provided adequate reasons for:

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rework; repair; reject; and accept as is

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I Further the " accept as is" disposition included assurance that the system or component would continue to meet all engineering functions including

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performance, maintainability, and safety.

The records indicate an adequate. quality assurance program in the area of

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procurement, storage, work activities and inspection of the Class IE

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electric systems.

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4.0 Electrical Systems and Components 4.1 Emergency Switchgear The 4,160 volt switchgear busses 21, 22, 23, and 24 were installed in their respective rooms within the control building. These four rooms and those similiar ones for Unit I are identified by a room number and the word emergency switchgear.

The inspector informed the licensee that the lack of unit and safety bus identification on these eight rooms potentially could lead to human error associated with testing and maintenance activities.

Similiar conditions exist for the four battery rooms per unit. This room identification deficiency is an unresolved item (86-09-01),

4.2 Motor Control Centers The installed motor control centers (MCC)in the reactor building and the recirculation MG set room of the turbine area were protected by a fire proof material in addition to plywood housing as required.

The MCCs were electrically heated.

The electric heat was not func-tional for MCC 20B129&130. The licensee was informed and took prompt corrective action.

The Long Term Maintenancc(LTM) program requires a surveillan:e for heater function every 90 days. However the inspectors review of the surveillance log noted that this surveillance was being performed every 30 days.

The inspector observed that an insulated heat pipe was installed parallel with MCC 20B129 & 130. The pipe was located above and passed over the rear portion of the MCC.

The licensee was informed of this potential hazard from either a seismic condition or a pipe leak. A review of the Q list indicated that these MCCs were not on the Q list although they were energized from the class 1E electric load center buses. A further review of the electrical schematic diagrams revealed that these MCCs were automatically deenergized for a LOCA condition.

However, they could be reenergized by operator action.

Each of the MCCs are energized from a separate division load center. This common pipe during v. leismic event or leak could challange two independent class 1E (twer sources. The licensee will investigate a resolution to this a<ters al commom cause failure between non safety and safety systens 4.3 Motor Operated Valves Four Limitorque 12" motor operated valves (MOV), located in Area 14 at elevation 249', were inspected on May 13, 1986. These valves were also reinspected with the licensee on May 14, 1986.

The following documents were applicable for this inspection and are listed in more detail in appendix A:

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Specification for Nuclear Service Valves Project Q List Maintenance Log Long Term Storage / Maintenance / Lubrication of Permanent Plant

Equipment & Materials Prior to Turnover Installation, Disassembly and Packing of Valves The visual requirements for valves in long term storage are:

Identification Rust moisture vapor barrier paper (RMBP) inside of valve body

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Desiccant placed in the valve body Moisture indicator in valve body and not reading 40%, pink.

Valve ends covered by non metal material Leads attached to megger valve motor Limit switch / torque switch compartment positioned to prevent liquified grease from entering Valve motor positioned to prevent liquified grease from entering i

motor housing The following were the valve inspection findings:

MOV 52-2F037 Core Spray

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Valve supported on sling, May 13,1986, with the operator 6" lower than valve body. A small amount of oil or grease was on the underside of the valve operator and also on the

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floor directly below.

l The valves had been raised from wooden blocks and supported

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by slings when the floor was painted.The length of time the valve was supported by the slings was not known.On May 14, 1986 the valve was supported by wooden blocks on the floor.

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No moisture indicator inside valve body.

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MOV 52-2F005 Core Spray

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Rust / vapor barrier, one side only.

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No desiccant in either side of valve body.

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No moisture indicator inside valve body.

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One end of valve not covered as required.

Rust / vapor barrier material provided only partial cover age over valve opening.

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Sand blast grit material inside open end.

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Light surface rust inside of open end. This extended toward valve center for 6 to 8 inches.

MOV E11 F0218 RHR Containment Spray

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Moisture indicator was pink, number 40%, indicating the desiccant should be changed.

I MOV E11 F0168 RHR Containment Spray

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No deficiencies were noted.

In addition to the above MOVs check valve 12 DCA-CKA052-208 was also supported in this area by slings on May 13 and 14. There was rust /

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moisture barrier paper (RMBP) inside of the valve. However, there was no desiccant material nor moisture indicator inside of the valve.

Long Term Maintenance personnel were contacted to determine storage /

maintenance requirements for these valves.

These valves arrived on site in 1978.

The Maintenance Action Cards (MAC) required that valves be protected from moisture by RMBP, desiccant, moisture indicator and the ends closed. The ends have a plastic window to observe the moisture indicator.

The MAC card for valve MOV 52-2F005 did not indicate that desiccant was required to be placed in the valve.

Valves 52-2F37 and 52-2F005 are currently schbduled for maintenance inspections. A revision of the maintenance instruction for valve 52-2F005 is required in order to add the desiccant requirements.

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The licensee's LTM personnel inspected these valves and corrected the above deficiencies on May 14 and 15 1986.

The MAC card for valve 52-2F005 revision has been initiated to add the desiccant placement to the inspection activities.

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The inspector determined that the above MOVs had been scheduled for on-site rework and testing. They will be reworked by BCI in accor-dance with the Limitorque rework program 8031-FM-4. They will be tested by PEC0 Field Engineering in accordance with the MOVATS program.

The inspector has the following concerns about MOV long term storage:

I The location of stored MOVs has been identified.

  • That all MOVs have been or will be scheduled for rework.

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The proper storage will be maintained after the MOVs are reworked.

  • This is an unresolved issue until the licensee addresses the above concerns.

(86-09-02)

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The Limitorque shop where the rework and testing is to be preformed

was toured by the inspector and PECO's QA personnel on May 15, 1986.

The testing of a large non Q valve was observed.The inspector dis-cussed the MOVATS program with the responsible licensee personnel.

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The MOVs are not required to have electric heaters energized while in long term storage.

In lieu of the heater, an approved "Hoffman"

rust inhibitor is sprayed on the limit switches and torque switches.

The inspector had no further concerns about MOVs long term storage and maintenance except as noted above.

4.4 Cables, Cable Raceways and Terminations 4.4.1 Control Room The inspector observed in process work in the Unit No. 2 control room. He witnessed the rewiring of indication light circuits with a larger conductor wire.

He verified that the rework was being con-ducted with approved procedures and materials, and that the wire crimping tools had also been calibrated.

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No unsatisfactory conditions were observed.

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4.4.2 Cable Spreading Room Electrical penerations were being installed through the east and west i

cable spreading room walls.

Existing and future cables will be routed through these penetrations.

Since both Unit I and Unit 2 share a common control room this work must be completed prior to routing cables through the ceiling into the Unit 2 main control board because the HVAC pressure boundary must be maintained per Unit 1 Technical Specification. A work package associated with these electrical penerations was reviewed by the inspector. This work

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package was W.P. C-0180-BC.0024, Rev.0, Backfill Blockout #2 Below

254', J line wall Control Room. Discussions about these electrical penerations was held with the responsible engineer.

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No unsatisfactory conditions were observed.

4.4.3 Battery Room The DC cables (500 KCM) in the 125/250 volt battery rooms are not terminated. The extra cable length is coiled, wraped with weld guard and supported by temporary rigging.

Two of the cables although adequately supported, required additional support to preclude poten-

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tial cable insulation damage. The minimum bend radius for these cables was not exceed. Nor was there any indication of cable jacket denting. However, since the station batteries will not be installed for a inderterminate time there was a concern potential cable insula-tion damage could occur if the cables were not fully supported. When notified of the potential for damage, the licensee took prompt corrective action which is documented in Surveillance Check Report number, 2E-197, dated May 16, 1986.

No unsatisfactory conditions were observed.

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5.0 Unresolved Item i

Unresolved items are matters about which more information is required in

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order to ascertain whether they are acceptable, an item of noncompliance or a deviation. Unresolved item identified during this inspection is discussed in paragraph 4.1 and 4.3 of this report.

6.0 Exit Interview An exit interview was held on May 16, 1986 with menbers of the licensee staff, denoted in paragraph 1, at the conclusion of the inspection. The

inspector summarized the scope and findings of the inspection at that time.

f No written material was provided to the licensee.

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i APPENDIX A Documents Reviewed

1.0 Final Safety Asalysis Report 8.1.6.1.14 Regulatory Guide 1.75, Physical Independence of Electric Syste.m 8.3.1.3 Physical Identificai.f on of Safety Related Equipment

.8.3.1.4 Independence of Redundant Systems Emergency Diesel Generator Connected Loads

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2.0 Project Q List, revision 19, 10/9/85 3.0 Construction Procedures (CP)

C-6 Recording Underground and Embedded Utility Installation, Revision 0, 6/11/85

D-1 Processing of Nonconformance Reports, Revision 2,

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5/1/86 i

D-7 Construction Administration Document i

Control, Revision 0, 12/19/85 i

E-1 Electrical Panel Modification, Revision 1, 3/13/86 E-2 Permanent Plant Cable Installation and Termination, Revision 0, 3/17/86 i

E-3 Electrical Raceway, Revision 0, 1/10/86 j

E-6 Non-NSSS Electric Equipment, Revision 0, 1/13/86 F-2 Receipt Inspection Storage and Withdrawal of

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Materials / Equipment a

G-3 Long Term Storage / Maintenance / Lubrication of

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Permanent Plant Equipment & Material Prior to i

Turnover M-4 Installation, Disassembly and Packing of Valves

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l 4.0 Project Special Provisions to Field Inspection Procedure j

G-3 Control of Nonconforming Items, SF/ PSP G-3.1, Revision l

12, 6/22/84

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5.0 Specification for Nuclear Service Valves, 8031-P-350, Revision 8, 4/26/83 6.0 Conduits & Cable Tray Notes, Symbols & Details, E-1406

1.0 General Notes i

2.0 Raceway and Dropout Cable Separation j

3.0 Raceway Numbering and Marking 4.0 Conduit Notes i

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7.0 Drawings Single Line Meter & Relay Diagram, MCC Load Tabulation

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E-66, Revision 5, 4/26/83 Schematic Diagrams E-159 Load Center SWGR-MCC Fdr Bkrs 440V Sheet 1, Revision 25, 1/14/83 Sheet 2, Revision 12, 6/24/83 i

Sheet 3, Revision 5, 8/28/84 E-160 Safeguard Busses-101 & 201 Safeguard Bus

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Feeder,4KV Sheet 1, Revision 19, 1/3/85 Sheet 2, Revision 9, 1/24/84 Sheet 3, Revision 17, 1/3/85

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Sheet 4, Revision 6, 3/13/85

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Sheet 5, Revision 0, 1/3/85

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E-162 Safeguard Buses-Load Center Transformer BKRS 4KV Revision 6, 12/14/82 E-163 Safeguard Buses-Load Center Transformer BKRS 4KV Sheet 1, Revision 12, 1/7/85 Sheet 2, Revision 1, 1/7/85 i

E-164 Safeguard Busses Generator BKRS 4KV Sheet 1, Revision 16, 5/23/84 8.0 Quality Records

PECO QA Audit Report j

E-214 BCI Unit 2 Cable Storage, 12/6-12/19, 1984

E-223 BCI QC Inspection-Maintenance Electrical

Equipment 11/6-11/19, 1985 QC Instruction Valve and In-Line Component Installation j

8031/P-1.30, Revision 10, 1/17/86 Nonconformance Report NCR 7751, 7/14/83, 100 Amp Disconnect removed from MCC 20D2030,open NCR 10337,8/25/84 Cutler Hammer, HFB, 25 AMP Failed Trip Setting Tolerance, open NCR 10599,8/15/85 Rocksbestos cable damage closed 8/21/85

NCR 10608,9/16/85 DG brush assembly inspection

closed 2/26/86

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NCR 10660,2/18/86 Rosemount Trip Unit Unacceptable j

closed 3/21/86 i

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