IR 05000387/1981020
| ML17139A533 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/12/1982 |
| From: | Ebneter S, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17139A532 | List: |
| References | |
| 50-387-81-20, 50-388-81-10, NUDOCS 8201290272 | |
| Download: ML17139A533 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-387/81-20 Report Nos.
50-388/81-10 Docket Nos.
50-387/50-388 Region I CPPR-101 License Nos.
CPPR-102 Priority B
Category A
Licensee:
Penns lvania Power and Li ht Com an 2 North Street Allentown Penns lvania 18101 Facility Name:
Sus uehanna Steam Electric Station Units
and
Inspection at: Allentown and Berwick, Pennsylvania Inspection conducted:
November 16-20, 1981 Inspectors:
A.
E. Finkel, Reactor Inspector Approved by:
S.
D. Ebneter, Chief, Plant Systems Section, Engineering Inspection Branch
~PM ate signed date signed Ins ection Summar
Ins ection on November 16-20 1981 Combined Re ort Nos. 50-387/81-20
~/
Areas Ins ected:
Routine unannounced inspection by one region-based in-spector of safety related electrical and instrumentation systems; review of previously identified items; facility inspection and di scussions with craft personnel.
The inspection involved 6 inspection hours at the corporate office in Allentown, Pennsylvania, 20 inspection-hours on the Unit 1 site and 14 inspection-hours on the Unit 2 site for one regional based inspector.
Results:
No items of noncompliance were identified.
r 820i290272 820ii3 PDR ADOCK 05000387 PDR
DETAILS 1.
Persons Contacted Penns lvania Power and Li ht Com an
K. Backenstoe, Nuclear Plant Engineering R. Beckley, Resident Nuclear QAE P. Brady, Lead Electrical, Project Construction J. Buczynski, Lead CSE
P. Capotosto, Quality Assurance Engineer
R.
Featenby, Assistant Project Director
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W. Gulliver, Supervising Engineer NQA Engineering
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S.
Kuhn, Senior Project Engineer Nuclear
MD Radvansky, Nuclear Plant Engineering
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A. Sleva, Project Engineer Nuclear Bechtel Power Cor oration
G. Bell, Lead Quality Assurance Engineer E. Brumfield, Quality Assurance K. Cook, Field Engineer G. Gelinas, Assistant Project Field QCE T. Klock, Construction Inspection E. Morgan, Assistant Field Engineer
W. Mourer,'ield Construction Manager W. Nelle, Quality Assurance U.S. Nuclar Re viator Commission
G.
Rhoads, Senior Resident Inspector J.
McCann, Resident Inspector
denotes personnel present at site exit meeting.
denotes personnel present at Allentown meeting.
The inspector observed work activities in progress, completed work and plant status in several areas of the plant during a general inspection of Units
and 2.
The inspector examined work items for obvious defects or noncompliance with NRC requirements or license commitments.
Particular note was taken regarding the relaying set points and the methods used to verify the instrumentation used in this task.
In addition, the inspector interviewed craft-and supervisory personnel encountered in the work areas.
No items of noncompliance were identifie.
Status of Previousl Identified Items Closed Licensee Identified Item 387/79-00-14:
PGCC/ACR Panel Connectors.
The inspector examined licensee documents PLA-506, NCR 3405 dated February 21, 1981 and FD1, WJIQ Revision I.
FDI, WJIQ, Revision I initiated a
100% visual inspection and pull test of all Unit 1 inner ring/relay/back row panel connectors terminated with No.
AWG wire.
The identification and rework cables were documented in NCR 3405.
Inspection for Unit one has been completed.
0 en Licensee Identified Item 388/79-00-14:
PGCC/ACR Panel Connectors.
See 387/79-00-14.
This item is not completed on Unit 2 and remains open.
Closed Licensee Identified Item 387/79-00-15 and 388/79-00-15:
American Insulated Wire (AIW cable deformities.
The licensee has completed a
qualification test program for 600 volt AIW cable.
The cable failed the 100 day test and has been replaced with cable from another cable manufacturer for inside containment use.
Reference paragraph 4 of this report for details of this test.
The inspector reviewed the Wyle Laboratories qualification test data for the AIW cable with the licensee.
A report on this test is scheduled to be sent to the NRC in December 1981.
This item is closed.
Closed Licensee Identified Item 387/80-00-19:
PGCC/ACR Raceway overfill.
The inspector examined the licensee documents E-296, Revision 2 raceway schedule and NEPO-10466 for maximum fill requirements.
To determine the
% fill, the following information is. required to be supplied to the raceway program.
The cross sectional area of each raceway and each type of cable used is entered into the raceway computer program.
The cross sectional area of cables used in a raceway are added together and checked against the raceway cross sectional area.
The percent fill is calculated and printed in the Raceway Schedule.
In reviewing the Unit 1 raceway schedule it was noted that the majority of raceways that were listed as overfi lied have been corrected by re-routing the cables in less filled raceways and by correcting cable, size input errors.
(Open)
Licensee Identified Item 388/80-00-19:
PGCC/ACR Raceway overfill.
Raceway fill has not been verified for Unit 2.
This item remains open.
Closed Licensee Identified Item 387/79-00-09 and 388/79-00-12:
PGCC/ACR Panel Inserts 72C and 73C.
The inspector examined the following licensee documentation, NCR 3748, dated May 3, 1979, NCR 3760 dated May 3, 1979, NCR 4326 dated September 10, 1979 and FDI-WJEA, Revision 0.
Pull testing of the connector cable and pin combinations were
performed on a
100% bases on the 72C
73C panel inserts.
The failed assemblies were repaired and tested at the site.
The inspector reviewed the test data and verified that the requirements of FDI-MJEA were met.
This item is closed.
Closed Licensee Identified Item 387/81-00-18 and 388/81-00-18:
Defective wire crimps on terminal lugs in the CRD HCU terminal boxes.
During the implementation of FDDR-KR2-525, Revision 0, it was found that No.
AWG conductors were pulling out of their crimped terminal lugs.
Based on the conductor lug problem identified in panel 2C0235, NCR 7612 was written and issued on February 28, 1981.
As a result of the disposition of NCR 7612 a random sampling of 418 terminal lugs installed in 38 HCU terminal boxes were pull tested.
The sample included 228 No.
AWG wires and 190 No.
AWG wires.
10 No.
AMG wires failed at less than the prescribed pull tension.
An inspection of the crimps made on the failed terminations indicated that many of the rejected cable/lug terminations were due to misalignment of the crimp tool when making the final mechanical connection.
Lugs were found crimped on the strain relief portion of the lug barrel rather than the portion of the lug in which the bare wire strands are inserted.
As a result of the test performed on the cable/lug combination, the licensee performed a
100% inspection of all No.
AWG cable/lug assemblies in the HCU boxes.
The testing and inspection'as performed in accordance with FDDR KRI-318, Revision 0.
The task was completed on August 5, 1981.
Of 1116 cable/lug terminations tested, 73 failures were identified.
All failed cable/lug terminations were corrected at the site and verified by gC.
The inspector reviewed the test documentation recorded in NCR 7612 and randomly inspected HCU electrical boxes.
This item is closed.
0 en Licensee Identified Item 387/81-00-28 388/81-00-28
(jualification of AIW cable.
The licensee notified the NRC on October 16, 1981 (PLA-945) that the American Insulated Mire (AIM) 600 volt cable failed the IEEE-383-1974 100 day environmental qualification test for the Susquehanna Units
and 2 profiles.
Based on the 100 day test the licensee replaced all 600 volt AIW cable inside Unit 1 containment. with Boston Insulated Wire (BIW) cable.
Approximately 24,000 feet of AIM cable was removed from the Unit 1 containment.
Unit 2 only had a few cables installed and the location and identification of these cables have been identified.
The Unit 2 AIM cables inside containment are scheduled for replacement.
The AIM cable did pass the 7 day LOCA test and based on this information the licensee is using the cable in class IE systems outside of containment.
This is to be documented in a letter from the licensee to the NRC due during the month of December 198 This item remains open.
0 en Licensee Identified Item 387/80-00-28 and 388/80-00-28:
PGCC flexible conduit grounding.
Flexible conduit is used to enclose electrical conductors in various fail-safe (deenergize to operate)
circuits which are part of the Reactor Protection System (RPS) of the PGCC/ACR system..
These include RPS, Nuclear Stream Supply Shutoff System (NSSSS)
and Neutron, Monitoring System (NMS) logic.
The purpose of the flexible conduit is to provide a low resistance path to ground under certain short-circuit conditions.
The inspector reviewed the engineering installation documentation for Unit 1 and
(FODR No.
KR1-607, Revision 0 dated October 30, 1981 and FOOR No.
KR2-561 Revision 0 dated September 28, 1981).
The construction work to install the conduit grounds had not started during this inspection period.
This item is unresolved pending NRC review of installation and inspection records.
0 en Licensee Identified Item 387/81-00-27 and 388/81-00-27:
Failure of Crosby SRV solenoids to operate at reduced voltage.
The Crosby valve solenoids which are part of the Automatic Depressurization System (AOS) failed to function at the low end of the DC voltage range when being tested to IEEE-323-1974.
The test identified that during the simulated 340'F, 105 psig steam LOCA condition, the solenoids required 130 VDC to be activated.
A requirement of this design specifies that the system voltage at the bus should be between 110YDC and 135VDC normally with an extreme low of 105VDC during peak loading or at the end of discharge during an emergency.
Therefore, the minimum voltage to actuate the solenoid is 105VOC under worst case condition and not the 130VDC + Tolerance that was considered to be the low DC voltage used in the qualification test.
This items remains open.
4.
Dll Cable (A)
Unit
The Dll cable is constructed of a Jacket of Hypalon and an EPR insulation over a copper conductor.
The use of 1/C¹10 AMG cable manufactured by AIW has been documented in the following licensee documentation:
PL1-7549, dated March 24, 1980, Cable Pulling, ER-100450, dated March 17, 1980, Cable Pulling,
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PLB-11306, dated May 20, 1980, Use of Single Conductor Cables, PLB-12324, dated April 23, 1980, Use of Single Conductor Cables, and FP-E-8 Revision 0, Part 2 Appendix A.
It appeared that during the installation of the Dll 1/C ¹10AWG cable in Unit
damage occurred to the cable during installation.
To verify that the installed cable in Unit 1 was still within specification requirements all Dll cable was tested to the requirements of FP-E-8, Revision 0, Part 2 Appendix A.
This specification required a 5000 VDC potential be applied for 5 minutes between the cable conductor and ground.
Cables that were below the leakage specification requirements were replaced.
The inspector reviewed the Unit 1 data and performed a random inspection of Dll cable installations.
No items of non-compliance were identified.
(B)
Unit 2 The use of the Dll 1/C No.
IOAWG cable is restricted to a specific use in the Unit 2 installation.
During construction, cable lengths of 50 feet or less can use the Dll AIW cable.
For pulls over 50 feet the Dll cable will be replaced with a type B12 and D13 cable to control installation problems associated with the Dll cable.
The inspector reviewed the test documentation for Unit
and the design installation documentation for Unit 2 to assure compliance within BLB-11306 and BLP12324 specifications.
The inspector had no further questions.
5.
Power Volta e and Rela Coordination Stud The licensee is preparing a power voltage and relay study for the Units
and 2 systems.
This study is scheduled to be complete within the 1st quarter of 1982.
The inspector informed the licen'see that this study would be reviewed by the NRC prior to licensing.
This item is unresolved pending NRC review of licensee report.
(50-387/81-20-01; 50-388/81-10-01).
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Fire Protection Racewa Thermal Coatin In complying with the Susquehanna Steam Electric Station Units
and
Fire Protection Review Report, dated January 1978 and Revised March,
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A 1981, the licensee is planning to use the TSI Corporation Thermolog material to coat raceways for compliance to Section 2.11 Minority Division Essential Cable Protection subsections (d) and (e).
The TSI Thermolog coating of 1/2 inch thickness is designed to add a
hour firing rating to raceways with a 12.5% cable derating for trays and a
7% cable derating for conduits.
The minority division raceway is obtained from a list of systems required for safe plant shutdown defined in Section 4.2 of the Fire Protection Review Report of March 1981.
This item is unresolved pending a review of the documentation associated with the applicat,ion, inspection, and qualification data of the TSI Thermolog Material by =the NRC.
(50-387/81-20-02; 50-388/81-10-02).
7.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncompliance.
Unresolved items are discussed in Details, Paragraphs 5 and 6.
The inspector met with licensee and construction representatives (denoted in Details, Paragraph 1) at the conclusion of the inspection on November 16, 1981 at the Corporate Office, Allentown, Pennsylvania, and at the Site on November 20, 1981.
The inspector summarized the purpose and scope of the inspection and identified the inspection findings.
The NRC Senior Resident Inspector was present at the exit meeting of November 20, 1981.