IR 05000440/1989018
| ML20247E738 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/16/1989 |
| From: | Gardner R, Kopp M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20247E726 | List: |
| References | |
| 50-440-89-18-EC, NUDOCS 8905260325 | |
| Download: ML20247E738 (16) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-440/89018(DRS)
DocF.et No. 50-440 License No. NPF-58 Licensee: The Cleveland Electric Illuminating Company 10 Center Road Perry, OH 44081 Facility Name:
Perry Nuclear Power Plant, Unit 1 Meeting At: Region III Office, Glen Ellyn, Illinois Meeting Conducted: May 11, 1989 Type of Meeting:
Enforcement Conference kM h V
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Inspector:
M. J. Kopp Sl/ 4 / 87 J
Date tb W Approved By: Ronald N. Gardner, Chief 5 f do Plant Systems Section Date Inspection Summary Meeting on May 11, 1989 (Report No. 50-440/89018(DRS))
Matters Discussed: Apparent violations of 10 CFR 50, Appendix B, Criterion XVI in regard to inadequate licensee corrective action to correct and prevent recurrence of previously identified environmental qualification (EQ)
deficiencies affecting 10 CFR 50.49 designated EQ Limitorque actuators and EQ Target Rock Solenoid valves. An additional topic concerning terminal box
moisture intrusion was also discussed. The analysis and disposition of the apparent violations will be presented in subsequent communications.
8905260325 890518 t
PDR ADOCK 05000440 Q
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i DETAILS i
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Persons Contacted f
a.
Cleveland Electric Illuminating Company (CEI)
A. Kaplan, Vice President, Nuclear Group R. Stratman, Director, Nuclear Engineering Department E. Riley, Director, NQAD B. Walrath, Manager, EPSS/NED R. Newkirk, Manager, Licensing and Compliance G. Dunn, Supervisor, Licensing and Compliance J. Lausberg, Supervisor, NQAD T. Stear, Senior Electrical / Design S. Litchfield, EQ Lead Engineer b.
U. S. Nuclear Regulatory Commission (USNRC)
A. Davis, Regional Administrator, Region III H. Miller, Division Director, DRS R. Cooper, Chief, Engineering Branch, DRS M. Ring, ChieiP, Projects Section 3B, DRP R. Knop, Branch Chief, DRP T. Colburn, Perry Project Manager, NRR P. Hiland, Acting Senior Resident Inspector, Perry B. Berson, Regional Counsel J. Ulie, Reactor Inspector, RIII B. Stapleton, Enforcement Specialist, RIII 2.
Enforcement Conference A:. a result of apparent violations of NRC requirements an Enforcement l
Conference was held in the Region III Office on May 11, 1989. The
preliminary findings, which were the basis for these apparent violations
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of NRC requirements were documented in NRC Inspection Report No. 50-440/890ll(DRS) and were transmitted to the licensee by letter dated May 5, 1989. The attendees of this conference are noted in Paragraph 1 of this report.
l The purpose of this conference was to discuss:
a.
The corrective action steps taken as a result of the 1987 NRC EQ inspection findin s documented in NRC Inspection Report No. 50-440/87013(DRS.
b.
The basis for the acceptability of the corrective actions taken in response to the 1987 NRC inspection findings.
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c.
.The' corrective actions currently being implemented to resolve-deficiencies with EQ Limitorque actuators, EQ Target Rock solenoid valves, and concerns regarding the~ sealing of EQ terminal boxes, such that moisture intrusion is prevented.
d.
The current Perry EQ organization, its functional responsibilities and interactions with other site organizations.
e.
The current programmatic controls utilized to ensure adequate implementation of the EQ program.
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f.
Corrective actions to be taken'arior to start-up from the current refueling outage that address tie quality of installed equipment from an EQ perspective.
In opening the conference,.the NRC representatives identified the following apparent violation of 10 CFR, Appendix B:
Criterion XVI - Corrective Action: Failure to identify and correct all instances in which unqualified terminal blocks were installed in 10 CFR 50.49 Limitorque valves, and all instances in which 10 CFR 50.49 Target Rock solenoid valves were not installed in the EQ tested configuration.
The licensee presented a summary of their review of the NRC findings, the root cause analysis, and immediate corrective actions taken. The licensee also presented specific and general corrective actions to prevent recurrence.of the apparent violations.
(See Attachment 1)
During this conference, the licensee stated that current walkdowns of EQ.
equipment, being performed to resolve NRC concerns, have identified'
additional EQ' deficiencies. 'These deficiencies involve the lack of T drains installed on Limitorque valves, and the use of terminal blocks inside containment in instrumentation in circuit applications.
'The evaluation and disposition of the issues discussed during the Conference will be documented in subsequent communications.
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ATIACIEENT 1
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CEI 3 esentation r
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NRC Region Sta
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Concerning Equipment Qualification Program at t7e Perry Unit 1 Nuclear Power Plant
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AGENDA 1. Introduction:
A. Kaplan Vice President, Nuclear Group
l 2. EQ Program:
R. Stratman Director,
- Organization Nuclear Engineering Department
- Function / Scope
- Interactions with other Perry Organizations
- Training
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3. Review of Actions Taken j
in Response to 1987 NRC EQ Audit report B. Walrath Manager, Engineering Project Support Section 4. Present Status of B. Walrath
- Terminal Blocks Manager, Engineering
- Target Rock Project Support Section Valves 5. Terminal Box Water B. Walrath Intrusion Manager, Engineering Project Support Section 6. Corrective Actions R. Stratman Director, Nuclear Engineering Department 7. Summary A. Kaplan 8. NRC Comments All j
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E0 Program Organization
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Scope / Functions Controls Interactions J
Training
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L Scope of Program:
L To provide and maintain qualification of 1E equipment in a harsh
environment to the requirements of 10CFR50.49 and NUREG 0588.. This includes all categories (A, B, C, D) as described in NUREG 0588.
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Seismic qualification of 1E devices in harsh and mild environments.
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Seismic qualification of active and passive mechanical equipment.
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Operability of active mechanical equipment.
Environmental qualification of mechanical equipment (nonmetallic) in a
harsh environment.
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E0 Element Functions
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.1)
Development and maintenance of Equipment Qualification auditable documentation.
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E0 reviews / analysis in support of the Perry Design Control Program.
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3)
Development'and maintenance of E0 specifications for maintaining
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configuration of.E0 equipment in the Perry Plant.
4)
Support of Perry Plant Operations via the Temperature Monitoring Program and Steam Leak / Equipment Effects Review.
5)
Support of Perry Plant Operations through specification of preventive maintenance requirements to ensure the qualified service. life of Perry Plant' equipment.
6)-
Development and maintenance of the list of' Perry equipment covered under 10CFR50.49.
7)
Review of documents (Nonconformance Reports, Operating Experience Reports, and other documents) for Equipment Qualification impact.
8)
Support of the equipment procurement process for equipment qualification requirements.
9)
Provided input in the development of checklists for Quality Assurance surveillance activities.
10)
Attendance' at industry meetings to terrain abreast of current nuclear industry equipment qualification issue.
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Controls / Interactions
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The following are formal / informal controls which presently exist between the E0 Element and other Project organization.
1.
E0 reviews procurement documents for proper consideration of E0 requirements when new/ replacement equipment is purchased.
(HCI-0402; HCI-0403; MCI-0404)
l 2.
As required by E0 applicability checks done for design changes, E0 performs 10CFR50.59~ applicability checks and safety evaluations and required seismic / environmental evaluations per 10CFR50.49.
(NEDP-0301; NEI-0357)
3.
Whenever any changes are made to the 0-List, E0 is notified to ensure that any required evaluations are performed, and Auditable File Packages are updated. Any changes or discrepancies are brought to the attention of the Engineering Support Unit.
(NEI-0355)
'4.
When requested, E0 assists Quality Assurance in the performance of audits and field walkdowns. This helps to ensure continued program compliance administratively and in the field.
(NOADP-1801; NOADP-1001)
5.
When corrective and routine maintenance activities are' performed, E0'
considerations are included per program requirements.
(PAP-0905; PAP-0906; IAP-0503) These procedures and detailed work instructions are governed.by Installation Standard Specification, (ISS-2700 and ISS-2701).
Any changes to procedures are reviewed for continued compliance with the EO Installation Standard Specifications.
In addition, E0 specifies maintenance replacements of limited life components.
6.
As requested by Licensing, Independent Safety Engineering Group, or the Reliability and Design Assurance Section, E0 performs technical l
evaluations and provides responses for IE Bulletins, Operating Experience Reports, etc.
NEI-0701 requires review of 100% of IE Bulletins and Notices for EQ impact.
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k iTraining (EO):
- o Equipment: training'for EQ Engineers.
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. Manager and Tech' staff training (INPO program).
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o QA 1010 (E0) for Maintenance and I&C planners / technicians,
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o ISS 2700 and 2701 for Maintenance /I&C/0A personnel.-
Training of outage contractor personnel to QA 1010 program.
O Documents reviewed during NRC' inspection 89-001.
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Response to 87-13 NOV Violation covered three areas:
a)
E0 auditable file problems.
b)
Problems with maintenance procedures.
c)
Installed equipment configuration problems.
Resolution included:
1)
Revision / clarification of E0 file packages.
2)
Revision of Maintenance requirements.
3)
Field verification /revork Field verification was 100% of all applicable components in a a.
harsh environment except for the following:
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Rosemount transmitters - a 10% inspection performed based on evaluation of existing maintenance requirements
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MSIV leakage control system blower motor junction box cover gaskets - only replaced 1 of 3 gaskets based on a review of maintenance history b.
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Pool swell deflectors
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"T" drain
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o Status of.Limitorque Terminal' Blocks
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History
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'I 1)l.Revork program.
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NRC Limitorque vendor inspection 3)
NRC 87-013 inspection
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Basis of Response-1)
Revork program 2)
Inspection of questionable motor operators (11 total)
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Spare Parts
.Recent' Problems-
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GE EB-25'
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KULKA 622 3)
Harathon 6004 4)
Inspection Status Root Cause
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1)
1982'Limitorque letter implementation
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Adequacy of Limitorque phase I in terminal. block' identification 3)
-Control of terminal blocks in Limitorque Phase III 4)
Error in developing list used for violation response 5)
Failure to recognize the deficiencies in the list Corrective Actions 1)
Specific training of all personnel performing inspection of Limitorque operators 2)
Inspection of all IE Limitorque in E0 Harsh Environment (166)
3)
Replacement of all terminal blocks with Harathon 300 4)
Capturing configuration on design output drawings
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Status of Target Rock Solenoids History
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Solenoid cover ~ bolts found-missing
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CEI analysis-
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3)
All Target Rock solenoids inspected Present Problem 1).
Solenoid cover bolt found " Loose"
^ Root Cause 1)
No torque instructions 2)
Inspectors not given' instruction to check bolts for tightness Corrective Action 1)
Specification revised
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100% target rock solenoids inspected and fixed (total of seven found with loose fasteners, one with missing lock nut)
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. Repetitive tasks written to inspect every refueling outage 4)
Vendors contacted when specific torque requirements are not given 5)
Expanded QA surveillance to cover other E0 equipment using enhanced checklists L:-______:__________-___________________-______-_--__-____-_-____-___--_____--_____-___-______-
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Terminal Box Vater Intrusion.
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Summary of' Design Approach o
Class lE' instrument circuits in the Dryvell, Steam Tunnel and Containment l-are spliced.
o Class lE circuits in.the Dryvell are spliced.
Class lE control circuits in the Steam Tunnel and Containment including o
penetrations may be terminated using qualified terminal blocks.
Class lE splices are made with approved RAYCHEM splicing kits.
o Qualified Conax assemblies are used to seal class lE equipment / components o
located in harsh environment where required.
Gaskets are installed for all safety related pull, junction, splice, and o
terminal boxes located in harsh environmental zones.
Vater tight conduit hubs / fittings, except where precluded by conduit o
thermal expansion considerations are used for conduit' entry to safety related terminal boxes, o
Containment cable transitions from trays to conduit'are configured to limit the intrusion of water.
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DRYVELL
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Design' Approach
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Closed conduit system Weep holes
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MSIV air packs
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Field Verification
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Raceway walkdown/ inspection Veep' holes
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STEAM TUNNEL
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Design' Approach
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Closed conduit system Veep holes
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Splices and Terminal Blocks
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Field Verification
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Veep holes CONTAINMENT 1.
. Design Approach Cable tray and conduit
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No veep holes required Terminal boxec
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Electrical penetrations 2.
Field Verification
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Terminal blocks / boxes
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Local instrument racks are spliced CONCLUSION Raceway design limits the possibility of water entering the conduit system thus ensuring the integrity of field terminal block. _ _ _ _ _ _ _. _ -
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i Corrective Actions
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All 1E Limitorques in harsh environment are being inspected-
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Developed enhanced. checklists for all plant E0 inspections
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OA is conducting surveillance of E0 Equipment
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Torquing requirement established for Target rock solenoid covers
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Location and qualification of Terminal Blocks in harsh environment t -
being verified
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Acceptability of raceways, conduits and associated boxes in' harsh environment with respect to vater intrusion have been verified
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Program to increase awareness of field condition of E0 equipment'
underway
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Joint meeting to improve communications planned
. PRESENTATION /NJC/2116
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