IR 05000387/1986007
| ML17146A358 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/22/1986 |
| From: | Finkel A, Jerrica Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17146A357 | List: |
| References | |
| 50-387-86-07, 50-387-86-7, 50-388-86-07, 50-388-86-7, NUDOCS 8605020119 | |
| Download: ML17146A358 (15) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
50-387/86-07 Report No.
50-388/86-06 50-387 Docket No.80-388 License No.
NPF-14 NPF-22 Licensee:
Penns lvania Power and Li ht Com an 2 North Ninth Street Allentown Penns 1 vania 18101 Facility Name:
Sus uehanna Steam Electric Station Unit 1 and
Inspection At:
Berwick Penns lvania Inspection Conducted:
March 31 - A ri 1
1986 Inspectors:
A. Finkel, Lead Reactor Engineer d
e Approved by:
J.
Jo nson, Ch f, Operational Programs Section date Ins ection Summar
Routine unannounced ins ection on March 31 1986-A ri 1
1986 Ins ection Re ort 50-387/86-07 and 50-388/86-06 Areas Ins ected:
Maintenance work request procedures and modifications, quality assurance/quality control interfaces, maintenance and testing of seismic monitoring instrumentation and quality assurance audits and sur-veillancee reports.
Results:
No violations were identified.
8605020119 860424 PDR ADOCK 05000387 9 'DR
'L
DETAILS 1.0 Persons Contacted Penns lvania Power and Li ht Com an
- R. Brouse, Electri.cal Maintenance Foreman
- T. Clymer, Nuclear guality Assurance Coordinator
~T. Dalpiaz, Instrumentation and Control Supervisor
"J.
Graham, Senior Compliance Engineer
"L. Onei 1, Maintenance Supervisor
"D. Thompson, Assistant Plant Superintendent
- J. Todd, Compliance Engineer U.S. Nuclear Re ulator Commission
~R. Jacobs, Senior Resident, Inspector
- L. Plisco, Resident Inspector
- Denotes those present at the exit interview on April 4, 1986.
2.0 Seismic Monitorin Instrumentation S stem The inspector reviewed the seismic monitoring instrumentation data and hardware installation for compliance with the criteria of 10 CFR 100, Appendix A, VI, (a), (3) "Required Seismic Instrumentation",
Regulatory Guide 1. 12, "Nuclear Power Plant Instrumentation for Earthquakes",
and the facility Technical Specifications.
Unit 1 and Unit 2 containments are assumed to respond identically.to a
given earthquake.
For this reason, instrumentation redundancy between units was not employed; identical seismic instrumentation was not installed in both units.
Equipment required by Regulatory Guide 1. 12, Revision 1,
for a Safe Shutdown Earthquake (SSE)
maximum ground acceleration of less than 0.3 g was implemented.
The Susquehanna SSE Maximum ground accelera-tion is 0. 1 g and the OBE maximum ground acceleration is 0.05 g.
2. 1 Seismic Instrumentation and Control Procedures The seismic monitoring instrumentation surveillance requirements are listed in TS Table 4.3.7.2-1.
Functional testing of the instru-mentation and sensors is described below:
Semi-Annual Functional Test of Strong Motion Seismic Instrumen-tation VT-05701, VT-15701, VT-25701, VT-05702, VT-15702, VT-15703 and VRS-05703, SI-099-201, Revision 2, October 31, 198 Month Calibration of Strong Motion Seismic Instrumentation, SI-099-301, Revision 2, January 28, 1986, and 18 Month Calibration of Peak Recording Accelerographs, SI-099-308, Revision 2, July 16, 1984.
In reviewing the documentation associated with the IEC test proced-ures, the inspector verified that the equipment met the requirements of the functional and 18 month calibration test procedures and was in compliance with the requirements of the Technical Specifications.
2.3 Seismic E ui ment Installation In verifying the seismic instrumentation installation and locations as listed in the TS, page 3/4 3-63, the inspector selected Control Room Panel OC696, ESSW Pumphouse Floor and the Containment Structure (Unit 1) sensors.
The triaxial accelerometers and sensor triggers were in protected enclosures and were observed to be clean when opened.
A review of equipment history records indicated that the response-spectrum analyzer in Panel OC696 was clean and and operable.
The Unit 1 Containment Foundation and ESW Pumphouse Floor instruments are tri-axial accelerometer channels with triggers.
The triggers are func-tionally tested and calibrated with their associated channels'o inadequacies were identified during the
. eview.
3.0 Administrative 0 eratin and Maintenance Procedure Review The procedures listed in Appendix A assure that maintenance activities performed on safety-related equipment and systems consider the following areas:
Administrative approvals for removing the system from service and returning it to service.
Maintaining the qualified configuration, System testing before, during and after work has been completed, Welding, open flame and ignition control, Cleaning of equipment during maintenance, Jumper control,
Criteria of inspection attributes and reporting deficiencies, Personnel qualification, Test equipment, calibration status Operations notification of system configuration during testing and restoration to normal, and Final review and acceptance of work performed.
The inspector reviewed the procedures listed in Appendix A to assure that the above criteria were included and that maintenance activities were clearly delineated.
3.1 Maintenance Procedures In addition to verifying that the maintenance procedures comply with the station administrative procedures',
the inspector verified that the requirements of the quality assurance program were complied with.
The maintenance procedures require that the Nonconformance Control and Processing Procedure NDI-gA-8.1.5, and the Noncompliance Procedure NDI-(A-8.1.2 be used if a nonconforming condition is found.
The inspector also verified that prior to using a procedure for the first time (including changes),
a walk through of the procedure is made by the maintenance engineer.
3.2 Units 1 and
Common E ui ment The Off Normal (ON) Procedures are written to support both Units 1 and 2 common equipment.
The inspector reviewed procedure NO. ON-000-002, Revision 3, Natural Phenomena.
This is is used if a Seismic Event occurs and activates Seismic Monitoring Panel OC653.
Activation of the panel OC653 initiates surveillance procedure SE-000-015, section 3.5 Earthquake.
This procedure is a step-by-step method and directs the operator through a sequence of actions to be taken if a Site Emer-gency, Site Alert or an Unusual Event occurs.
The operators interviewed by the inspector were knowledgeable of the above referenced procedures.
No violations were identified.
4.0 Work Authorization S stem The inspector reviewed the work authorization system associated with elec-trical maintenance on components and systems to ensure that the program was in accordance with site administrative control. 1 Work Authorization The selected work authorization (WA) packages associated with valve limitorque operators and the reactor protection system equipment were reviewed by the inspector to verify that the following criteria were considered.
Control room notified of the WA scope and approval obtained as necessary, The WA routed to gA for review and classification, Referenced procedures identified with caution notes listed, Functional testing listed with re-verification of system or component status performed after task completed, Records reviewed and signed by the responsible maintenance engineer after WA completed, and, If additional work is required to be performed on the subject after the original WA has been closed, another WA is issued.
Following a review of maintenance records and discussions with con-trol room operators, the maintenance engineer, and quality control inspectors the inspector determined that the above criteria are included during the WA review cycle.
4. 1. 1 Limitor ue Work Authorizations The following WAs were for repair of packing on Limitorque operated valves and were performed per the preventative maintenance schedule for the component listed.
WA-V60189, System No. 83, Equipment No.
HV2011 WA-S63612, System No. 34, Equipment No.
HD17630B WA-P53233, System No.
51A, Equipment No.
HYE211F015A WA-S42772, System No. 50, Equipment No.
HV15012 The inspector verified that the criteria listed in paragraph 4. 1 were compiled on each of the four WA listed above.
WA orders V60189 and S63612 required additional work to be performed above the requirements listed on the original WA.
In each case a
new request (Y63348 and S52126)
was issued to perform additional work at a later dat. 1.2 Reactor Protection S stem RPS Work Authorizations Before work was authorized on RPS channel Bl a safety:ievaluation was performed and the results was approved by the site PORC.
Maintenance of the General Electric HFA relays in the Bl channel during operation put the plant in the following condition:
Division 2 Half Scram (Bl Channel),
Disabled associated Division 2 annunciator, and Disabled associated computer point, and associated display Control system and temperature monitoring system points.
Additional impacts involved various partial isolation signals (logic only).
To address the above areas the licensee issued procedure MT-158-B01, Revision 0, dated March 11, 1986, RPS "Bl" Channel HFA Relay Contact Inspection.
This procedure was referenced in the following WA pack-ages with attached cleanliness requi rements and equipment release forms attached.
WA-S52869, System No.
WA-S52858, System No.
WA-S52857, System No.
WA-S52867, System No.
WA-S52863, System No.
WA-S52862, System No.
58, Equipment No.
C72AK10B 58, Equipment No.
C72AK6B 58, Equipment No.
C72AK7B 58, Equipment No.
C72AKBB 58, Equipment No.
C72AK3B 58, Equipment No.
C72AK3F The inspector reviewed the WA packages listed above and verified that the work was completed within the acceptance criteria listed:in main-tenance procedure MT-158-B01.
In the "Action Taken" page of the WA, the technician noted that both the normally closed (NC) and normally open (NO) contacts had to be adjusted.
The NC contacts had to be adjusted 1/8" while the NO contacts were adjusted for 1/16" to 1/8".
Based on the results of this testing the maintenance engineer is re-commending that Unit 2 have its RPS HFA relay settings verified in a manner similar to the Unit 1 test.
A WA has been generated to per-form a similar test on the Unit 2 HFA relays during the outage planned for the third quarter of 1986.
No violations were identified.
5.0 Back Shift Ins ection On April 2, 1986 the inspector performed a back shift inspection of work in progress on the ESS Bus 1A (1A201) to verify that the criteria of Work Authorization P-52330 was complied with, that standard plant procedures
.
were followed and the TS paragraph 3.8.3.2 was complied wit The electrical maintenance supervisor was knowledgeable of the WA require-ments.
All notifications and tagging requirements were documented and the operators were notified of the work to be performed.
Verification that the site power distribution system was in the configuration defined in TS paragraph 3.8.3.2.
was completed by the operators.
Cleaning of the trans-formers and checking for carbonization, rusting, corrosion and overheating was performed to the criteria of procedure MT-GE-009, paragraphs 5.51,and 5.5.2.A.
The electrical maintenance personnel were briefed on their task prior to the work being performed.
No violations were identified.
6.0 uality Assurance Pro ram A review of the licensee's quality assurance program in the area of elec-trical maintenance was performed to verify compliance with the require-ments of the Final Safety Analysis Report (FSAR) section 17.2.14, Inspec-tion, Test and Operating Status, and section 17.2. 18, Audits; and, Techni-cal Specification (TS) section 6.5.2, Susquehanna Review Committee (SRC).
6. 1 Audits and Surveillances A licensee audit of the maintenance function was completed during the end of March, 1986 with the audit exit meeting held during the week of March 31, 1986.
The audit report results and any corrective action will be reviewed by the NRC during a future routine inspection of this site.
The inspector reviewed four recent quality assurance surveillance reports:
86-021, March 5, 1986, Electrical Activities Relay Test,86-013, February 12, 1986, PMR Implementation,85-156, January 1,
1986 and 86-022, February 5, 1986, In-Process Electrical Maintenance WAs.
The inspector verified that the QA surveillances were perform-ed in accordance with the QA program requirements.
The four survei l-lance reports findings had their respective corrective actions completed and attached.
6.2 ualit Assurance Review of Safet -Related WA's During the review of Work Authorizations referenced in paragraph 4. 1 of this report, the inspector verified that the Work Classification section of the WA Form was checked by quality assurance personnel.
The inspector also verified that hold points were selected and iden-tified by the quality assurance organization.
No violations were identifie.0 Intermediate Ran e Monitor IRM Drive Connectors During installation inspection of the Intermediate Range Monitor ( IRM)
cable connectors (NRC Inspection Report 50-388/83-19, page 19), the inspec-tor questioned the radiation dose and the effect of the dose on the Teflon insert in the SRM/IRM connectors (items UM2Q1195C, UN2Q1199C, VM2Q1197C, VM2Q1201C, XM2Q1196C, Xm2Q1200C, YM201198C and YM2Q1202C).
The licensee stated that they would perform an analysis of the teflon insert to deter-mine its adequacy for the present application (Ref.
Nonconformance Report No. 83-1299, November 8, 1983).
During this inspection period the inspector requested the engineering anal-ysis and the bases that the licensee used to determine that the connectors have not been affected by the radiation dose to date.
The data analysis was not immediately available and will be provided to the NRC resident inspectors at the site.
The method used by the licensee to track this item will be reviewed by the NRC during a future routine later inspection of this facility.
No violations were identified.
8.0 Exit Interview The inspector met with licensee management representatives (see section 1.0 for attendees)
at an exit meeting on April 4, 1986.
The inspector summarized the scope and findings of the inspection at that time.
At no time during this inspection was written material provided to the licensee by the inspecto APPENDIX A DOCUMENTS REVIEWED AO-QA-103, AD-QA-120, February
AD-QA-141, 1986, AD-QA-142, AD-QA-143, AO-QA-302, 1986, AO-QA-307, October
Ad-QA-410, AO-QA-411, AD-00-417, 1985, and AD-QA-422, Protective Permit and Tag System, Revision 5, June 30, 1982, Nonconformance Reports-Control and Revision, Revision 2, 1986, Fire Protection-System Status Control, Revision 2, February 5,
Control of Ignition Sources/Cutting and Welding Permits, Fire Watch Procedure, Revision 2, November 6, 1984, System Status and Equipment Control, Revision 4, February 27, Electrical and Mechanical Bypass Control, Revision 5, 1985, Plant Modification Program, Revision 4, January 23, 1985, Plant Modification Design Control, Revision 8, July 29, 1985, Plant Performance Monitoring Program, Revision 0, January 18, Surveillance Testing Program, Revision 6, June ll, 198 gr