IR 05000344/1986005

Insp Rept 50-344/86-05 on 860324-28.No Noncompliance or Deviation Noted.Major Areas Inspected:Procedures & Followup on Info Bulletins,Notices & Open Items

ML20203J885
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/09/1986
From:	Dodds R, Pereira D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20203J879	List: IR 05000344/1986005 ML20203J874
References
50-344-86-05, 50-344-86-5, GL-85-22, IEB-79-02, IEB-79-2, IEB-85-001, IEB-85-002, IEB-85-1, IEB-85-2, IEIN-85-074, IEIN-85-091, IEIN-85-74, IEIN-85-91, NUDOCS 8604300274
Download: ML20203J885 (7)

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. U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report No. 50-344/86-05 Docket No. 50-344 License No. NPF-1 Licensee: Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name: Trojan Nuclear Plant Inspection at: Rainier, Oregon Inspection Condu - d: arch, 4-28, 1986 Inspector: m Stdse !f[[ D. B. Pereira, Reactor Inspector Date Signed Approved by: ~

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R. T. Dodds, Chief D4te' Signed Reactor Project Section 1 Summary: Inspection During the Period of March 24-28, 1986 (Report No. 50-344/86-05) ) I Areas Inspected: Routine, unannounced inspection of procedures, and follow-up I on Information Bulletins, Notices and open item The inspection modules numbers 30703, 42700, 92701 and 92703 were used for guidanc Results: No items of noncompliance or deviations were identifie i I h O

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DETAILS ,

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1. Persons Contacted

*R. P. Schmitt, Manager, Operations and Maintenance
*C. A. Olmstead, Manager, Quality Assurance Department
*J. D. Reid, Manager, Plant-Services
*C. H. Brown, Operations Branch Manager, Quality Assurance
*A. Puzy, Office Supervisor
*S. Bauer, Engineer, Nuclear Safety and Regulation Department H. F. Moomey, Trojan Resident, Oregon Department of Energy
*S. Richards, Trojan Resident, U. S. Nuclear Regulatory Commission
* Denotes attendance at exit interview conducted at Trojan Nuclear Plant
, on March 28, 1986.

2. Plant Procedures Program ! The overall plant procedures, temporary procedures and procedure changes were examined for conformance with Technical Specifications, regulatory requirements, and licensee commitments. The technical adequacy of several procedures were examined to ensure that desired action and modes of operation were consistent. The inspection included a review of the following procedures:

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General Plant Operating Procedures - 4 Startup Operation, and Shutdown of Safety-Related System Procedures - 6

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Abnormal (Alarm) Condition Procedures - 6 i Procedures for Emergencies and Other Significant Events - 12

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Maintenance Procedures - 13

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Administrative Procedures - 10 The inspection also included a review of checklists, procedures, and ' related forms in the Control Room, Instrument and Control Area, and Technical Support Center to ensure they are current with respect to j revisions and temporary change The inspection results of the Trojan procedures program were as follows:

; The inspector reviewed 34 procedural changes and verified that the I

revised procedures were in conformance with technical specifications and license revisions.

i The inspector verified that procedures written during the past year l were properly approved and did not conflict with technical specifications requirement The inspector. verified that changes made to procedures written during the past yeur were modified and maintained in accordance with NRC requirements.

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 . The inspector verified that overall procedure content was consistent with technical specifications requirements, The inspector performed a review of checklists and related forms in the Control Room and verified that they were current with respect to

the effective revision maste The inspector performed a review of current procedures in the Control Room, in the Instrument and Control Area, and in the Technical Support Center and verified that the procedures were current with respect to proper revision and temporary changesLas

; compared to the effective revision maste The licensee's plant procedures program activities appear to be conducted in accordance with the licensee commitments, regulatory requirements, and l Technical Specifications.

j No violations or deviations were identified in,this area'. l _ 3. Follow-up on Previous Inspection Findings i " (Follow-up Item Information Notice (IN) No. 85-74 Closed) Station Battery Problems This information notice describes problems that have occurred with d lead-acid station batteries at several nuclear power plants. Recent IE inspection of operating facilities indicate that several widespread deficiencies may exist in the operation and maintenance of station batteries. These deficiencies were attributable to a

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variety of causes, including licensee error, inadequate knowledge of batteries by maintenance technicians and supervisors, and inadequate procedural guidanc , Trojan Nuclear Plant performed an evaluation per Operational Assessment Review (OAR)-85-104 which was completed on March 17, 1986. The evaluation follow-up per 0AR-85-104 results !

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Cooper PAT Inspection (November 1984)): Trojan maintains records of battery tests. The rated-load discharge test is conducted in accordance with MP-1-14 with manufacturer's recommendation McGuire PAT Inspection (February 1985): Trojan does not float charge individual cells in an on-line batter l Susquehanna PAT Inspection (February 1985): Trojan's procedure for maintaining station batteries (MP-1-14) incorporates the manufacturer's recommendations and is consistent with IEEE Standard 450-197 San Onofre PAT Inspection (March 1985): Battery capacity tests have been regularly scheduled and performed. The test results

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have been appropriately reviewed and found to meet both Technical Specifications and manufacturer's specification Based on the above OAR evaluation, it appears that Trojan has not experienced problems in the operations and maintenance of their station batteries. Information Notice 85-74 is close b. (Follow-up Item Information Notice (IN) No. 85-91 Closed) > Load Sequencers for Emergency Diesel Generators

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This information notice describes potential design deficiencies that could bypass load sequencers, thereby causing loss of redundant emergency diesel generators (EDG's). Duane Arnold nuclear plant discovered that an accident signal and the loss of the standby ;

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transformer (a source of offsite electric power) would cause engineered safety feature (ESF) loads to be applied as a single , block load onto the EDG's (the source of onsite electric power), wh'ich would likely cause loss of both EDG' The inspector interviewed licensee personnel concerning Trojan's i load sequencers for the emergency diesel generators. The results of the interviews indicated that Trojan load sequencers do not apply ESF loads as a single block load onto the EDG's, but that they load ! sequentially, i.e. one load at a time. For Trojan, when an ESF , signal occurs, the loads are stripped off the ESF buses or emptie ' Then the EDG's are started and loaded onto the ESF buses and when the EDG's are at full voltage and power, then the load sequencers '

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commence bringing loads onto to ESF buse If a loss of offsite power occurs and then offsite power is restored, the ESF buses are , isolated from offsite power and require deliberate synchronizing of frequency and voltage (i.e. paralleling) prior to energizing the ESF buses via offsite powe l l Based on the above examination, Trojan appears to not have the ! problem of bypassing ESF load sequencers. This Information Notice 85-91 is close .

' c. (Follow-up Item IE Bulletin No. 79-02 Rev. 2 Closed) ) , Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts I&E Bulletin 79-02 Revision 2 was issued to PGE on November 8,197 ' This bulletin and revisions required each licensee to examine the design application of concrete anchor bolts in light of criteria contained in the bulletin and to examine quality control (QC) records and/or conduct a sampling program of installed anchor bolts 1 to verify that the concerns raised by the bulletin were properly ' , dealt wit Inspection Report 79-25 provided additional details but did not close IE Bulletin 79-02 Rev. 2 due to the fact that Trojan was still evaluating and conducting test The licensee's letters dated November 21, 1979 and December 8, 1979 provided complete answers to IEB 79-02 Rev. 2 requests. IE Bulletin ' 79-02 Revision 2 is considered closed. The inspector interviewed ;

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. personnel and reviewed correspondence to verify that testing, modifications, and inspection programs were completed in accordance with bulletin requirement d. (Follow-Up Item 85-36-02 Closed) Maintenance Procedure (MP)-1-5 failed to list the test equipment used in the procedure. The inspector reviewed MP-1-5 Revision 3, dated January 14, 1986 and the revision lists the test equipment used in the procedure. Follow-up item 85-36-02 is close e. (Enforcement Item 85-36-01 Closed) Violation - Failure to record i

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proper data for PICT-11-1 Data Sheets Periodic Instrumentation and Control Te.t (PICT) 11-1 Power Range , Setpoint Test requires data to be recorded in PICT 11-1 data sheets. l Specifically, step 7.2.3 requires measuring and recording Power i Range High Voltage which the licensee failed to perform on several l PICT 11-1 data sheet In the licensee's letter dated 4 December 6, 1985; the licensee's response stated that they reviewed I additional PICT 11-1 data to ensure that the Power Range High Voltage was within Specification on those occasions when the data were not recorded. The licensee stated that no deviations from the required voltage were foun In addition, the licensee revised PICT 11-1 to improve the format and readability of the procedur PICT 11-1 was revised with Revision 14 dated January 27, 198 Enforcement item 85-36-01 is considered close f. (Enforcement Item 85-36-01A Closed) Violation - Failure to record test equipment type used during PICT PICTS 2-1, 2-2, 2-3, 3-1, 3-2, 4-1, 4-2, and 4-3 require the test equipment type and tag number of test instruments used to be recorded in the PICTS data sheets. Test equipment type and tag data were not recorded on several data sheet In licensee's letter dated December 6,1985, the licensee's response stated that in each of the stated cases where the equipment type and tag data were not recorded on the data sheets for the ramp generator used, each of the deficient data sheets have been corrected. The correction was possible because there is only one ramp generator onsite. The inspector verified that the deficient data sheets were correcte Enforcement item 85-36-01A is considered close g. (Follow-up Item Generic Letter 85-22 Open) Potential For Loss of Post LOCA Recirculation Capability due to Insulation Debris Blockage This generic letter describes a generic safety concern regarding LOCA-generated debris that could block PWR containment emergency dump screens, thus resulting in a loss of recirculation or containment spray pump net positive suction head (NPSH) margin. The

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licensee was still in the process of reviewing this generic letter via Operational Assessment Review (OAR) 86-18 which is due May 16, 1986. Item will remain open until 0AR 86-18 is completed and another inspection is performed on GL-85-2 h. (Follow-up Item Inspection Report 84-05-1 Open) Use of Commercial Grade Materials This inspection report item concerns the licensee's improper use of commercial grade materials. The licensee has issued a Nuclear ' Division Procedure (NDP) No. 300-3 Revision 0 dated February 19, 1986 which provides guidance for documenting engineering evaluations of commercial grade items used in safety-related applications (Quality Level Code C ).3 This revised procedure does not become effective until the training program has

{ conducted training and fully implemented, about July 1, 1986. This item will remain open until the commercial grade material procedure j has been fully implemented and another inspection performe ;

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i. (Follow-up Item Inspection Report 84-05-04 Open) Inconsistent Implementing Procedures This inspection report item concerns a review of implementing j procedures which do not address the regulatory guides and standards referenced in Section 2, Appendix A of the licensee's Nuclear Quality Assurance Program for operations. The licensee is reviewing a Cygna Report for implementation and follow-up of these item Item will remain open until implementing procedures have been issue J. (IE Bulletin 85-01 Open) Steam Binding of Auxiliary Feedwater Pumps This IE Bulletin informed licensees of a potentially serious safety ' problem involving the inoperability of auxiliary feedwater (AFW) ~l pumps due to steam binding. The licensee has responded via letter dated February 28, 1986 stating the following actions have/are being j accomplished in response to IE Bulletin 85-01:

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1) 01-8-2 - operating procedure for the AFW system was j revised to require that the safety-related AFW pump discharge piping be checked for elevated temperatures approximately five minutes after each time a pump is ! stopped. The inspector verified that Revision 19 was l

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2) The inspector verified that operations personnel were trained on the possible causes and symptoms of back l 1eakage through the AFW pumps, and on 01-8-2 procedural l change, during a retraining course in October 'and November j 198 '

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3) Routine operating test prodedure (POT 24-1) was revised in December 1985 to providetfor monitoring AFW pump discharge piping temperatures. The revised procedure now includes a requirement to monitor AFW pump discharge piping temperatures at least once each shift. The inspector verified that the procedure change was issued and shift monitoring of AFW pump discharge piping temperature is being don ) The 18 month test procedure for the AFW system (POT 5-3) has been revised, but not yet reissued, to require performance of a full-system-pressure leak test for the second-off AFW pump discharge check valve . 5) Contact surface thermometers will be installed on the AFW pump discharge piping during the 1986 refueling outag This IE Bulletin will remain open pending completion of 1; ems 4) and 5) abov D-C.35 (IE Bulletin 85-02 Open) UV Trip Attachment of DB-50 RT Breakers This IE Bulletin informed licensees of recent reactor trip breaker reliability problems, to assure that facilities which have not yet installed the automatic shunt trip modifications are performing undervoltage trip attachment (UVTA) for margin testing of the reactor trip breakers (RTB's). The licensee has

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issued OAR 85-123 which will conduct an inspection of the UV Trip attachments per maintenance request (MR) 86-0422 which is scheduled for the refueling outage in 8 This item will remain open pending completion of 0AR-85-123 'and inspection of the result < 4. Exit Interview The inspector met with the licensee representatives denoted in paragraph 1 on March 28, 1986, and summarized the scope and findings of , , the inspection activitie !

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