IR 05000346/1986024

Insp Rept 50-346/86-24 on 860804-07.Deficiencies Noted: Failure to Demonstrate Qualification of Rockbestos Coaxial Cable & Two Solenoid Valves

ML20207H831
Person / Time
Site:	Davis Besse
Issue date:	12/17/1986
From:	Potapovs U, Wilson R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:
Shared Package
ML20207H811	List: IR 05000346/1986024 ML20207H806
References
50-346-86-24, NUDOCS 8701080150
Download: ML20207H831 (15)

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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No.: 50-346/86-024 Docket No.: 50-346 License No.: NPF-3 Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit No. 1 Inspection At: Oak Harbor, Ohio Inspr- ion Conducted: August A to 7, 1986 (conclusion of Inspection No. 50-346/86-010 of February 24 to 28, 1986)

Inspector: 4h IE!!7!86 R. C. Wilson, Equipment qualification & Test Engineer Date i

l Also participating in the inspection and contributing to the report were:

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_ Potapovs, Chief, Equipment Qualification Inspection Section, IE >

A. Gautan, Reactor Inspector, Region III R. Smeenge, Reactor Inspector, Region III

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M. Jacobus, Member of Technical Staff, Sandia National Laboratories M. Yost, Consultant Engineer, Idaho National Engineering Laboratory l D. Jackson, Consultant Engineer, Idaha National Engineering Laboratory r

Approval: LM (2/7df Uldis Potapovs, Chief. Equibment Qualification Inspection Date Section, Office of Inspec; ion and Enforcement 8701080150 DR 861219 ADOCK 05000346 PDR

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INSPECTION SUMMARY Inspection on August 4 to 7, 1986 (Inspection Report No. 50-346/86-024 Areas Inspected: Special anrounced inspection to review the licensee's imple-mentation of a program per the requirements of 10 CFR 50.49 for establishing and maintaining the qualification of electric ecufpment within the scope of 10 CFR 50.49. Conclusion of Inspection No. 50-346/86-010 of February 24 to 28, 198 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

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belo Name Report Paragraph Item Number Potential Enforcement / Unresolved Items: Rockbestos coaxial cable 4.D.(1) 50-346/86-024-01 Amphenol penetration assembly 4.D.(2) 50-346/86-024-02 ASCO solenoid valves 4.0.(3) 50-346/86-024-03 Open Items: BISCO LOCA seal 4.D.(4) 50-346/86-024-04 Maintenance procedures /86-024-05 Licensee-identified concerns /86-024-06 Licensee tracking system /86-024-07

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DETAILS PERSONS CONTACTED 1.1 Toledo Edison Company (TED)

• J. Williams, Jr., Senior Vice President-Nuclear

• B. R. Beyer, Nuclear Projects Director

• P. C. Hildebrandt, Nuclear Engineering Group Director

, * L. Stewart, Nuclear Training Director

• T. J. Chiles, Materials Manager

• S. J. Smith, Assistant Plant Manager, Maintenance

• J. W. Fay, Nuclear Engineering General Manager

• P. W. Jacobson, E0 Coordinator

• J. E. Moyers, Quality Verification Manager

• R. F. Peters, Jr., Licensing Manager

• R. M. Cook, Acting Compliance Supervisor

• J. Freels, Nuclear Support Training Manager J. Haverly, Fire Protection Engineering Manager

• J. C. Buck, QA Auditor

• T. M. Broad, Licensing Engineer

• S. J. Strout, Licensing Engineer T. Isley, Lead I&C Engineer

• K. T. Bell, EQ Engineer W. Muggy, Engineer 1.2 Consultants to TED

• W. F. Emerson, Davis-Besse EQ Program Manager, Stone & Webster

• 0. J. Mavro, Consultant, Stone & Webster

• F. G. Hertrich, EQ Engineer, Stone & Webster

• D. Schulz, Engineer, Stone & Webster

• P. J. Maiorano, EQ Support, Stone & Webster P. A. DiBenedetto, Consultant, DiBenedetto Associates >

• A. H. Bock, Jr., EQ Support, DiBenedetto Associates

*N. Patel, Project Engineer, Impell l

• A. Shafii, Principal Engineer, Impell l *A. Bokhari, Senior Engineer, Impell

• Gaballa, Senior Engineer, Impell

• Sitler, Senior Engineer, Impell

• Tesfaye, Senior Engineer. Impell

• A. Ayash, EQ Support, Impell

• L. Basinski, EQ Support, Bechtel

• T. Vovides, EQ Support, Bechtel

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• B. Tondi, EQ Support, Bechtel

! *T. M. Maynard, Jr. , EQ Engineer, ANC

• K. Nesser, EQ Support, Flex

• B. Hobart, EQ Support, Manpower H. Woodward, Representative, Brand Industrial Products 1.3 USNRC -

P. M. Byron, Senior Resident Engineer D. C. Kosloff, Resident Engineer

• Denotes those present at the exit meeting on August 7, 1986

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.- . PURPOSE The purpose of this inspection was to continue and complete the review of the licensee's 10 CFR 50.49 program that was initiated February 24 to 28, 1986 for Davis-Besse Nuclear Power Station, Unit N . BACKGROUND IE Inspection Report No. 50-346/86-010 transmitted June 13, 1986 covers the background of the licensee's EQ activities and reports the findings of the inspection conducted February 24 to 28, 1986. At that time the NRC deter-mined that the licensee's program was not sufficiently developed and imple-mented to permit meaningful final inspection. The inspection report iden-tified 32 unresolved items that would be included in a continuation of the

_ inspection prior to the plant restart anticipated late in 198 Based on discussions between the NRC and the licensee, the inspection was continued and concluded during the period August 4 to 7,1986. Most of the members of the original inspection team were able to return at that time. In the interim, the licensee issued two more LERs involving EQ:

i LER 86-021 addresses Raychem splices and LER 86-022 covers two steam generator level transmitters. Possible relevance _to the EQ program of LER 86-005 (Bisco fire seals) was also identified. These are in addition to previously addressed LERs85-023 and 86-00 . FINDINGS The August 4 to 7 inspection completed inspection activities begun in February and described in Inspection Report 50-346/86-010. Some aspects

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of the Davis-Besse EQ program were judged to be completed in February, l

such as the EQ Master List; they were not re-reviewed. The following areas were covered in the August inspection:

- Fifteen new or revised procedures not available in February were inspected .

- Licensee actions on the five LERs cited above were inspected, together with some additional open areas identified to the inspectors by the licensee on August 4

- Three tracking systems covering all uncompleted EQ-related work were examined

- Twenty-four previously inspected EQ files in which deficiencies had been found were re-inspected

- Two additional EQ files were inspected

- Previously inspected components of four equipment types for which defects had been found were re-inspected, along with some additional components of the same types

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- Multiple samples of ten additional equipment types were also examined in walkdown inspections Based on the inspection findings, which are reported in more detail below, the inspection team determined that the licensee has implemented a program to meet the requirements of 10 CFR 50.49, although some deficiencies were identified. Davis-Besse was shutdown for the entire period from June 9, 1985 (when the loss of feedwater transient occurred) until after the August 7, 1986 completion of this inspection. As discussed in Inspection Report 50-346/86-010, the licensee conducted a complete re-evaluation of his EQ program during that period and extensively reported findings by LERs and other means. The inspection findings reported herein cover the Davis-Besse EQ program as of August 7, 1986 and do not attempt to docunent earlier deficiencies that were corrected by that dat EQ Program Procedures The NRC inspectors examined the licensee's EQ procedures which have been revised and implemented since February 28, 1986. The following procedures were examined to verify implementation of corporate and

site policies and procedures for establishing and maintaining the environmental qualification of electrical equipment in compliance with the requirements of 10 CFR 50.4 Administrative Procedures AD 1807.00, " Control of Conditions Adverse to Quality," Revision 1, dated May 13, 198 AD 1809.00, " Station Environmental Qualification Program," Revision 0, with Temporary Modification Request T-10503, dated April 9, 198 AD 1844.00, " Conduct of Maintenance," Revision 15 with Temporary Modification Request T-10505, dated April 9, 1986.

l AD 1844.02.01, " Control of Work (MW0)," Revision 1, with Temporary l

Modification Request T-10422, dated March 13, 198 A.D 1845.02, " Facility Change Request Initiation," Revision 0, with Temporary Modification Request T-10507, dated April 9, 198 AD 1845.03.0, " Facility Change Request Initiation," Revision 0, with Temporary Modification Request T-10508, dated April 9,1986.

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AD 1847.00 " Station Material Control," Revision 10, with Temporary l Modification Request T-10510, dated April 9,1986.

I Nuclear Facility Engineering Procedure j

f NFEP-010, " Processing Facility Change Requests," Revision 4, with Procedure Modification Form M-174, dated July 25, 198 NFEP-011 " Conceptional Designs," Revision 4, with Procedure i

Modification Form M-153, dated May 8, 1986.

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NFEP-020, " Design Work Packages," Revision 7, with Procedure

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Modification Form M-175, dated July 24, 1986.

NFEP-040, " Vendor Submittals," Revision 3, with Procedure Modification Fom M-177, dated July 25, 198 ,

NFES-070, " Procurement," Revision 2, with Procedure Modification Form M-180, dated July 25, 198 NFES-072, " Purchase Requests for Engineering Items or Services,"

Revision 3, with Procedure Modification Form M-125, dated Ap.il 11, 198 Nuclear Engineering Procedures (Procedures previously identified as NFEPs)

NEP-NE-041, " Vendor Manua'is," Revision 0, with Procedure Modification Form M-178, dated July 25, 198 NEP-NE-160, " Environmental Qualification Program," Revision 1, dated July 31, 1986.

I Administrative Procedures AD 1844.03 and AD 1844.14 were previously

' identified as be'ng revised during the NRC February 1986 EQ inspec-

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tio Administrative Procedure AD 1844.03, " Control of Maintenance l

Instructions," has been deleted. The licensee has replaced main-l tenance instructions with maintenance procedures. AD 1844.14 has

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been replaced with NMP-DS-2064, " Requests for Assistance," Revision 0, dated June 30, 198 All the procedures reviewed by the NRC inspectors were found to be satisfactory. The licensee has now issued maintenance procedures

"or each piece of EQ equipment. Maintenance procedures for specific equipment were reviewed by the inspector reviewing the individual EQ documentation packages. The computerized list, " Preventive Maintenance for Environmental Qualification," used to identify and schedule maintenance requirements for each piece of EQ equipment is being continually updated to include all EQ equipment. Pending NRC i review of the implementation of appropriate maintenance / surveillance procedures for EQ equipment, Maintenance procedures is considered Open Item 50-346/86-024-0 Licensee-Identified Concerns Including LERs The NRC inspectors reviewed the status of licensee actions for five LERs. The inspectors reviewed the status and scheduling of licensee actions.

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(1) LER-86-006 - Environmental Qualification Program Not Adequately Established All appropriate physical work has been completed and inspected by QC/QA for this LER. The following Facility Change Requests (FCR) and Maintenance Work Orders (MW0) are in the final plant acceptance sign-off cycl FCRs MW0s Item 86-029 2-86-0029-03 Rosemount Transmitters86-016 2-86-0016-01 SOR Pressure Switches86-008 2-86-008-01 Foxboro Pressure Transmitters (2) LER 85-023 - Error in the High Energy Line Break Analysis in the Auxiliary Building The following Impe11 Corporation Reports provided analyses for High Energy Line Breaks (HELB) causing a harsh environment in the Auxiliary Building:

02-1040-1335, " Evaluation of Equipment Qualification Concerns Associated with AFW Break Study," Revision 1, dated November 198 , " Evaluation of Envirormental Conditions from Auxiliary Pump Turbine Steam Supply Ruptures," Revision 2, dated March 198 , " Evaluation of Environnental Conditions from

. Auxiliary Feedwater Pump Turbine Steam Supply Line Rupture,"

Revision 1, dated March 1986.

f Safety-(related rooms electrical equipment located in the affected500, 5 l

l List and the environmental profiles for these rooms have been mcdified and incorporated into DB1-100, " Environmental l

Conditions," Revision 1, dated April 2,1986. Environmental l

l qualification for the safety-related equipment added to the

! EQ Master List, as a result of LER-85-023, has been established by the license (3) LER 86-022 - Environmental Qualification of Steam Generator Level Transmitters This LER identified steam generator level transmitters LTSP9A3 and LTSP983 as necessary to mitigate a small break LOCA or HELB, but as having field cable connections / splices that were not environmentally qualified for submergence. The licensee performed l

l a design review and determined that the existing installations could be modified to qualify the equipment. At the conclusion l

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of this audit the licensee identified Facility Change Request 86-0164 as the controlling document for the above modifications, and reported having the required hardware onsite to complete modification During this review the NRC inspectors examined "Small Break LOCA operating procedures and effectiveness of Emergency Feedwater (EFW) spray for B&W plants," B&W Document ID.77-1141270-00 dated February 1983. This evaluation indicated that SBLOCA's having i break sizes greater than 0.02 square feet did not require EFW to j maintain core cooling as the break is large enough to depres-surize the primary system below the secondary system, and that this break size did not set a minimum level control setpoint for EFW control. TED also reported that they are in the process of approving calculations which indicate that for break sizes smaller than 0.02 square feet the tran.imitter connections will not be submerged during the period they perform their safety function. In addition to this evaluation, TED is committed to qualifying these transmitter connections prior to startup by raising the electrical connections above the flood leve (4) LER 86-021 - Inadequacies in Raychem Installations On May 14, 1986, TED issued LER 86-021, which reported that during training sessions on Raychem terminations / splicing they had discovered that their past practices may have resulted in improper terminations / splices being installed in the field on 10 CFR 50.49 designated EQ equipment. The following discrep-ancies were reported:

- Improper Raychem tubing sizes due to use of incorrect Raychem ki Deficient overlap of Raychem tubing onto wire insulatio .

- Shrinkage of Raychem tubing over fabric cover of wires

causing inadequate bonding and potential leakage paths.

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- Improper bending of heat shrink covers to accommodate installation in junction boxes.

- Improper finished diameters on Raychem heat shrink cover.

l TED initiated a Raychem splice evaluation program committed to i

identifying and qualifying all EQ Raychem splices prior to startup. As of August 19, 1986, TED had identified 1087 EQ connections, of which 622 have been inspected for deficiencie Of the 622 conrections examined, 354 were Raychem splices of l which 232 have been repaired. During this review the NRC l

inspectors examined over 60 Raychem splices inside and outside the containment. Discrepancies were found to be identified and tracked through nonconfornance tags with the exception of

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splices on braided wire jackets at accelerometer 2E4263, Elevation 636' inside the containment. The licensee stated they had not yet performed an inspection on this eauipmen All other observed deficiencies were tagged for repair or qualification by testin Where the individual wires of a cable are not qualified, TED uses Raychem cable breakout kits with an outer sleeve. If the individual wires (conductor with jacket) are qualified, then TED-designed kits are used with the individual wires spliced and an outer sleeve provided for strength only, not ior sealing purpose TED reported that they had conducted testing of Raychem and TED-designed splices and had determined that test samples with and 1.1 inch sleeve overlaps were environmentally qualified for at least five years in appropriate environments. Aging for more than a five-year life was incompatible with the plant restart schedule. Sample splices over a #8 bolt were also successfully tested. Results of these tests had not yet been documented, but would be in place prior to startu (5) LER 86-005 - Improper Boot-Seal Installation This LER addresses improper axial seam overlap in boot seals used as negative pressure boundaries, fire barrier penetrations, and flood protection barriers. The inspectors were concerned that problems with these seals might also apply to BISCO LOCA seals used for environmentally sealing cable entrances to 10 CFR 50.49

, equipment. Specimens of both types of seal were inspected during the plant walkdown, and both designs were reviewed with TED personnel and a BISCO representative. The inspectors concluded that concerns reported in the LER and other NRC inspection activities do not apply to the BISCO LOCA sea (6) Additional Open Items On August 4 the licensee identified to the NRC inspectors four additional open areas affecting EQ that had been identified during the outage. In each case one or more apparently viable solutions were identified, but additional work on equipment and/

or documentation was required to close out the item. In each case TED comitted to resolving all related EQ concerns prior to restart.

I HELB/ Fire Seals - The TED Appendix R task force identified i

fire seals with the potential to blow out if their design

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pressure is exceeded; this could cause additional vent paths between rooms, possbly creating additional 10 CFR 50.49 harsh environment areas. TED stated that a study indicated l

, that minor rework of the fire seals would eliminate the potential EQ problem.

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.. ... Room 314 Blowout Panels - Re-evaluation of criteria for the blowout panels requires changing the release pressure from 0.5 to 1.0 psid. The inspectors reviewed TED's preliminary evaluation showing that HELB environmental conditions used for EQ would not change, basically because the pressure transient is fast and the environmental effect of blowing out the panels is large. Documentation of the new analysis and its impact on EQ was not yet complet Auxiliary Steam HELB Conditions - HELB analyses in the USAR of the auxiliary steam system took credit for operation of two non-safety grade isolation valves. Re-evaluation showed that in the Auxiliary Building other HELBs bound the auxiliary steam line break. This is not the case in the Service Water Buildirg, where evaluation indicated that portions of the piping could be upgraded seismically so that it can be. classified as a moderate energy line, removing it from HELB consideration. Additional, TED

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planned to increase preventive maintenance on both valves as part of a PM program scheduled for implementation by September 1, 198 Westinghouse Five Star Breaker - This circuit breaker feeds a bus powering the PORY block valve. Attempts to qualify the breaker by similarity analysis were unsuccess-

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ful. An FCR was initiated to either replace the breaker

' with a qualifiable type, or to rewire the circuit to another breake A future NRC inspection will verify that the licensee has completed actions en all of the LERs (except 86-005) and the Additional Open Items listed in section 4.B of this inspection report. Licensee-identified concerns constitutes Open Item 50-346/86-024-0 ! Tracking Systems ,

The NRC inspectors reviewed three trecking systems that had been

! established by TED for monitoring EQ related work being performed during the outage. These systems are:

(1) " Status of Environmental Qualification Packages." Although all 84 packages were virtually completed as far as review and analysis work is concerned, documentation of maintenance history and final walkdown was not completed for several packages. This list, arranged by package number, shnws the

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status of each packag (2) " Preventive Maintenance for Environmental Qualification."

This list shows, by plant ID number, the status of any preventive maintenance required during the outage for all master list equipment.

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(3) " Environmental Qualification FCR and NCR Status." LER 86-006 documents discovery of 153 unqualified components. For these components ar.d all other EQ-related Facility Change Requests and Nonconformance Reports this list shows work status. It is arranged by NCR and/or FCR. number and shows plant ID numbers for all affected equipmen The NRC inspectors examined these lists in detail, both program-matically and by using specific samples from other activities during the inspection. Only one error was found: maintenance signoff of three Limitorque operator packages was prematurely (by one day)

entered in the EQ Package list. The inspectors concluded that the tracking systems appeared to be complete and accurate. Because of the importance of these systems in ensuring that necessary work is perfomed, a future NRC inspection will verify that the work shown on all three lists is completed. TED did advise by telephone on November 17, 1986 that all required work was completed, except that approximately eight Maintenance Work Orders lacked final signoff Licensee tracking systems constitutes Open Item 50-346/86-024-0 Environmental Qualification Files The NRC inspectors examined 37 EQ packages in February. Unresolved items were described in inspection report 50-346/86-010 for 24 packages. These 24 packages were re-inspected in August, together with two additinnal files not reviewed in February. In the following discussion the four files found deficient in August are addressed first, followed by brief identification of the resolution of February deficiencies for the remaining files. In report 50-346/

86-010 the deficient files were identified in section 4.D as paragraphs (1) through (24). In this report these items will be identified with a new paragraph number and the same title as before; the "old" paragraph number will also be give .

Some of the EQ packages still lacked final signoffs because maintenance -

history or final walkdowns were not complete. In such cases the NRC inspectors determined that the " Status of Environmental Qualification Packages" tracking system list of August 6,1986 showed the correct package status. The single exception noted, for Limitorque operator packages, is described in section 4.C above and was correr t~d before the exit meetin (1) Rockbestos coaxial cable type RSS-6-113, package DB1-047, old item (9) - This cable is used in the high range radiation monitor. Most of the February concerns were resolved: the new Rockbestos type test report and a similarity evaluation were included in the file; beta radiatinn unluation for the short length not enclosed in conduit showed that only the outer 6 mils of the jacket exceed the tested 1.4 x 10E8 rads dose; and the file did address functional performance criteria. However, it was not clear that performance would be acceptable for low

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radiation levels combined with thenna11y-induced high leakage currents. On November 17, 1986 TED advised the NRC by phone that the system vendor (Sorrento Electronics, formerly General Atomics) had re-analyzed leakage current data and shown that Reg. Guide 1.97 criteria are satisfied. Since this equipment was procured after February 1983, qualification to 10 CFR 50.49 is required. Rockbestos coaxial cable constitutes Potential Enforcement / Unresolved Item 50-346/86-024-0 (2) Amphenol penetration assembly, package DB1-003A, old item (13) -

Incomplete portions of the file were completed. LOCA test data 4 to show that the 1.0 Megohm insulation resistance criterion was satisfied were still not in the file. However, prior to the end of the inspection, TED located some test information that had been developed because of operational problems. This testing showed insulation resistance values near 1,000 Megohms, which is acceptable as shown by the new TED generic accuracy calcu-lation described under Samuel Moore cable in section 4.0.(12)

below. Amphenol penetration assembly constitutes Potential Enforcement / Unresolved Item 50-346/86-024-0 (3) ASCO solenoid valves, plant ID SVICS1181 and 2, package DB1-004C, old item (23) - The maintenance requirement discrepancy was resolved. The SCEW sheet stated that these valves are exempt from qualification, but the file requires qualification for 235 F and the cable entrance seal was not shown to be qualifie TED determined that in fact these valves are exempt from quali-l fication and changed the file accordingly during the inspectio ASCO solenoid valves constitute Potential Enforcement / Unresolved Item 50-346/86-024-03.

f (4) . BISCO LOCA seal, package DB1-048, old item (5) - Although the l

minor documentation omissions originally identified had been

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completed, during re-inspection the 20-year cualified life

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restriction was determined to be omitted from the Preventive .

Maintenance Data Base. This deficiency was corrected prior to the exit meeting. BISCO LOCA seal constitutes Open Item 50-346/86-024-02.

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Limitorq)ue operator packages DB1-037C, D, and F, old items (1)

were resolved, except for documentation of completing some hardware modifications still to be performed that are addressed in section 4.E.(2) of this report and that were covered in the appropriate licensee tracking system (6) Deutsch relay, package DB1-012, old item (4) - The test report was added to the file and the analyses complete (7) Pyco RTD, package D81-042, old item (6) - The Pyco RTDs have been replaced with Conax RTDs covered by package DB1-064. This package was inspected and found to be acceptable, except for installation work and maintenance procedures covered by the tracking system _ _ _

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(8) Magnetrol level switch, package DB1-024, old item (7) -

Documentation that these components need not be qualified was complete (9) Rosemont 1154 transmitter, package DB1-03E, old item (8) -

The maintenance schedule has been updated to reflect the 15-year qualified life. The installation work was not completed, and was being tracke (10) General Atomic radiation element, package 081-016, old item (10) -

Letter BT-17010 (package reference 9) was added to the file to cover system qualification, including detector accuracy and connector qualification. The detectors were re-mounted in a veritical orientation, the same as the test specimen; this was verified during the walkdown inspectio (11) Raychem WCSF-N splices, package DB1-029, old item (11) - Beta radiation has been acceptably addressed by analysis based on Raychem type testing to 1000 Megarads beta in combination with

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aging and DBA testing. This concern is specific to the high range radiation monitor. Raychem splices are addressed generically in section 4.B.(4) of this repor (12) Samuel Moore instrumentation cable, package DB1-031, old item (12) - The generic accuracy calculation for cable in 4 to 20 milliamp transmitter circuits was corrected and included in the file. Although the analysis did not consider cable length correction for insulation resistance, the analysis contained sufficient conservatism to justify the omission. The new analysis considered that at temperatures above 220 F, during the first 17 minutes of the accident, circuit accuracy need not be considered because all actions would be automatic and no operator action is require (13) Buchanan terminal block, package DB1-002, old item (4) - *

Inclusion of the generic accuracy calculation and addition of other documentation completed this packag (14) BIW instrumentation cable, package DB1-007, old item (15) -

Inclusion of the generic accuracy calculation and addition of

other documentation, including a letter from BIW to help

' establish similarity between the installed and tested cables, completed this packag (15) Endevco and TEC charge convertor and transient shield, package DB1-138, old item (16) - Bechtel letter BT 16228 documenting qualification was added to the file and the tracking system covers remaining installation work.

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(16) Kerite power and control cable, package DB1-023, old item (17) -

The revised generic accuracy calculation has been added to the file, as has a statement that any submerged cables would complete safety functions prior to submergency. The two cables under 18

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month surveillance have been re-analyzed. Containment air cooler cable description has been clarified by stating that separate cables provide high and low speed power, and an ESAS signal changes the coolers to low speed. The low speed cable is qualified for 40 year (17) Conax electrical conductor seal assembly, package DB1-008A, old I item (18) - TED resolved an apparent similarity problem by providing Conax drawings and catalogs showing that part number N21009-01 is a feedthrough assembly included in the entire ECSA, part number N-11006-53. With regard to thread sealants, TED showed that Conax Test Report No. IPS-546 Rev. B covers qualifi-cation of ECSAs with Series 300 stainless steel parts mated to each other using no thread sealant, and that Tite Seal is used only to reduce gallin (18) Rosemount 1152 transmitters, plant ID LTSP9A6, 7, 8, and 9, package 081-030B, old item (19) - Definition of service require-ments was added to the file, and Maintenance Work Orders were

issued to replace 0-ring (19) Westinghouse decay heat pump motor, package DB1-036C, old item

(20) - Acceptable references for lead wire splice and lubricant packages were added to the file. The inspector reviewed these i packages (DB1-049C and 081-055, respectively),motormaintenance I procedures MP1700.74 Rev. 00 and MP 1410.33 Rev. 6, and the

" Davis-Besse Lubrication Manual" Rev. 3. These documents were i

found to satisfactorily support motor qualificatio (20) Lubricants, package DB1-055, old item (21) - This package was prepared after the February inspection. Review of the package '

l, determined that it lists equipment requiring qualified lubricants l and supports qualification of the lubricants used in each appli-cant. The inspectors also determined that packages for selected equipment using lubricants properly reference this file. TED agreed to revise the " Davis-Besse Lubrication Manual" to refer-

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ence this fil (21) Stanwick terminal block, package DB1-032, old item (22) - The concern addressed the impact of corrosion observed during the

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walkdown inspection on the claimed 40 year qualified life. TED addressed this concern in intra-company memorandum AN86-0964 i dated July 30, 1986. Although no specific commitments were made, the memo stated that surface corrosion of passive components by itself will not degrade operability, but it recomended a preventive maintenance surveillar.ce program to perform sampling inspections in selected plant areas during refueling outages, followed by corrective action such as cleaning or covering with

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an environmentally qualified coating where warranted, together with evaluation of the extent of the problem. Active components were stated to be covered by system tests developed as part of Tech Spec and ASME Section XI actions, but additional evaluation was recommende (22) Rees push button switch, package DB1-044, old item (24) - The test report and evaluation for ambient pressure were added to the file, and affected components were identified by plant ID numbe E. Plant Physical Inspection Multiple specimens of 18 types of equipment were examined in the February walkdown inspection. Concerns were identified in inspection report 50-346/86-010 for four types of equipment. In August the specific components found deficient in February were re-inspected, together with additional samples of the same four equipment type Multiple samples of ten additional equipment types were also inspected in the August walkdown. The qualification status and general condition of the equipment was excellent in August, clearly better than in Februar No significant deficiencies were found in the August walkdown inspection. TED disposition of the February findings is summarized belo (1) Namco limit switches - Metal tags had been secured to the switches, stating that the return spring was modified and giving the new model number. Orange maintenance tags addressed the missing cover screws, which were on order, and supporting documentation was in place.

l (2) Limitorque operators - The operators had been cleaned, conduit secured, wires properly terminated, gaskets replaced where ,

needed, etc. Installation of some T-drains or weep holes remained, but documentation existed and was covered in the tracking system (3) Decay heat pump motor - Deficiencies observed earlier had been

,

corrected in February. In August, work was being performed on l

other equipment in the area. The motors and area appeared to l

be acceptable except for a clean white rag lying on the frame

'

between the No. 2 pump and motor.

l (4) Stanwick terminal blocks - No evidence of corrosion or excessive l

dirt was found in several selected junction boxes. Corrosion l

is discussed further in section D.(21) above.

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