IR 05000344/1980025
| ML19351E449 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/03/1980 |
| From: | Carlson J, Sternberg D, Willett D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19351E441 | List: |
| References | |
| 50-344-80-25, NUDOCS 8012100134 | |
| Download: ML19351E449 (6) | |
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U. S. ::UCLEAR REGUL\\ TORY C0:0!ISSIO i OFFICE OF I!;SFECTIC 1 A!!D E!; FORCE!E!;T R2GIO!i V 50-344/80-25 Report !!o.
Docket !!o.
50-3dd License :o.
flPF-1 safeguards Group Licensee:
Portland General Electric Company 121 S.
',1. Salmon Street Portland. Oreqon 97204 Facility riame:
Troian Inspection at:
Painier, Orenon Inspectica c6Educted:
.0etober 20-23, 1980 IO ll
!ND Inspectors: \\
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un J. O. Carlson, Reactor i]ispecgot 36te < signed m
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n. J. Will6tt, Reactor Inspector Date signed
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Date Signed Approved 2y:
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... c.g D. il. Sternberg, Chief, Reactoq Project Section 1 Date Signed Peactor Operaticns and i;uclear Support Branch Su:=ary:
Inspection on October 20-23, 1930 (Report Io. 50-344/80-25)
Areas Insnected:
Poutine, unannounced inspection of maintenance; procedures and results; surveillance procedures and results; design, design changes, and modifications; organization and administration; response to IE bulletins and Circulars and followup on previous inspection items; also included independent inspection effort. The inspection involved 40 inspector hours onsite by two fiRC insocctors.
Resul ts:
!!o deviations or items of noncompliance were identified.
RV Form 219 (2)
b'012100 1D ;
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DETAILS 1.
Persons Contacted
- C. P. Yundt, General Manager
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- C. A. Olmstead, Manager, Technical Services
- R. P. Barkhurst, Operations Supervisor
- D. F. Y,ielblock, Manager, Plant Services
- A. S. Cohineyer, Engineerina Supervisor
- J. D. Peid, OA Supervisor
- R. J. Talbert, Corporate CA G. Mickel, Instrument and Control Supervisor D. Swan, Maintenance Supervisor
- U. T. Dixon, Oregon, DOE The inspectors also interviewed other licensee employees during the course of their inspection. These included corocrate and plant staff, enoineers, and licensed operators.
"Present at Exit Interview.
2.
Licensee Action on Previous Insnection Findinns (JC-80-01 Closed)
Vencor letter:
Swenson Division of Whiting Corporation advised NRC of potential problems with their Radioactive Waste Evaporator.
The letter indicated that two units may have been installed at Trojan.
The licensee nas determined that this equipment was not 4 nstalled at Trojan and the letter was in error.
3.
IE Eulletin/Ca rcular Followuo l
The insnection included followup on licensee actions related to recent IE Culletins and circulars.
The bulletins and circulars had been forwarded to and reviewed by cognizant members of the licensee's organization.
Inspection findings relating to the bulletins and circulars reviewed during the inspection were as follows:
IE Bulletins 79-03 and 79-03A, Longitudinal Heid Defects in SA-312 Type 304 Stainless Steel Pipe (0 pen): The licensee's reply dated April 20,1979, to the original IEB 79-03 stated that no pipe manufactured by Youngstown was in use at Trojan.
The scope of concern was widened by JEG 79-03A, however, and an additional response is expected frcn the licensee in December 1930.
IE Bulletin 79-0$C, Nuclear Incident at Three Mile Island (Closed):
The resident inspector has completed reviewing the completed actions described in the licensee's response.
Regarding the long torn action for adding an automatic trip of the reactor coolant pumns, this will be handled on a generic basis through
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the Uestinghouse owners group.
IE Bulletin 79-17, Pipe Cracks in Stagnant Borated Water Systems at PUR Plants (Closed):
The inspector verified the licensee's actions committed in the response was completed.
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IE Bulletin 80-16, Potent?al fiisapplication of Rosemount Pressure Transmitters (Closed): The licensee does not use Rosemount Pressure Transmitters in any safety related applications.
IE Culletin 80-19, Failures of l'ercury-Wetted flatrix Relays designed by Combustion Engineerino (Closed: The licensee does not use this type of relay in the lonic natrix of the Peactor Protection System.
IE Bulletin 80-20, Failures of Westinchouse U-2 Control Switches (Closed): The licensee determined that no switches of of type described are installed in safety related systems at Trojan.
IE Circular 80-04, Securing of Threaded Lockina Devices on Safety Related Equipment (Closed): The licensee had existing procedures addressing this item.
In addition, maintenance personnel have had training courses on this subject.
IE Circular 80-09, Problems with Plant Internal Communications Systems
.(Closed): The licensee reviewed their ccmmunications system response to a loss of offsite power. At Trojan the executive system and internal bell system use a battery as a backup power source.
In addition, interference of radio transmissions on electronic eouipment had been resolved previously.
IE Circular 80-11, Emergency Diesel Generator Lube Oil Cooler
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Failures (Coen): The licensee evaluated the problem described in this circular, along with other determining factors and decided to replace the solder types of coolers with rolled type coolers for joining the tubes to the tube sheet.
In addition, the licensee is changing the rust inhibiter to a type recommended by the nanufacturer.
4.
Desinn, Casien Changes, and Modifications As part of !!RC's Systematic Assessment of Licensee Performance (SALP)
Program, this area has been determined to be weak in the licensee's program; consequently, increased emphasis will be given to design change control by the inspector. The inspector commenced the review of the licensee's program for handling design changes and modifications.
The inspector reviewed the following procedures to determine the licensee's program:
a.
Quality Assurance Procedure-3: Design Control.
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Administrative Order-5-1:
Plant Changes and Alterations c.
Generation Engineering Procedure 200-5:
Design Change Control.
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The inspector verified the licensee's program met the criteria of 10 CFR 50.59 and technical specifications.
The inspector reviewed four design change packages to determine the content of the packages and the rethod for closing the completed design chan g.
flo major problems were identified.
The inspector noted that the licensee has been upqrading the design control program internally through the corporate Quality Assurance Department.
The inspector requested an updated status of the outstanding task force actions, flo items of noncompliance or deviations were identified.
5.
Ornanization and Administration The inspector determined that no key onsite changes had taken place in the licensee management since this item was last reviewed.
A ma.ior reorganization is taking place in the corporate structure of t..e licensee. The inspector verified the licensee reported the changes to NRC in the form of a technical specification change.
After the reorganization has been completed, the inspector will ccmplete the review.
llo items of noncompliance or deviations were identified.
6.
Surveillance Testina of Safety Related Systems The inspector reviewed several periodic operating tests (P0T's) to verify that the licensee has established and followed a program, that adequately ascertains the performance of technical specification parameters,in the individual safety related surveillance tests.
The following POT's were reviewed:
POT-9-3 Chemical volume control system - boric acid transfer pump:
Alternation and valve verification POT-1-3 Reactor Coolant System - Leakage evaluation P0T-2-3 Safety injection - Monthly ECCS valve performance P0T-4-3 Containment Spray - Valve Performance POT-12-2 Standby diesel Generators - Loss of offsite power, Diesel Automatic Start P0T-25-2 Safeguards test panel / Actuation tests and test of manual initiation switches.
The inspector verified that the test frequency was met, as specified in the technical specifications.
Inspection records and prerequisite preparation records were reviewed for required: Acceptance criteria, technical review, operational checks when returning equipment to service and adminstrative approvals.
No deviations or items of noncompliance were identified.
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7.
Maintenance Activities of Safety Related Systens The inspector reviewed several naintenance requests; procedures to do specific maintenance on equipment and the related equipment history files, to verify that the licensee has established and adhered to a program that adequately naintains the performance of safety related equipment within the parameters outlined by technical specifications.
The following systens were reviewed:
Safety injection Reactor coolant -
MP-5-5, Remove and replace reactor coolant pump seals Containment Spray Chemical and volume control system -
MP-12-5-Valve motor operators Diesel Generators -
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MP-12-7, Emergency Diesel Generator Plant Pressurizer level The insoector verified: The functional test of instruments used; the required administrative approvals were obtained; required functional testing and calibration completed - prior to return to service and the availability of quality control records.
t!o deviations or items of noncompliance were identified.
8.
Indeoendent Inspection The inspector reviewed several plant safety and administrative orders and evaluated their integration into the maintenance and surveillance programs.
The following plant safety and administrative orders were reviewed:
PS-3-30 Holdout and tagging procedures A0-3-9 Maintenance Requests.
A0-3-14 Safety Related Equipment Outages The inspector reviewed the lac naintenance and surveillance program.
Areas evaluated included: equipment clearances, administrative approvals, test equipment calibration and record keeping. The inspector interviewed the I&C supervisor, maintenance electrical SLpervisor and several of their staff, reguarding their; interfaces, understanding and responsibilities within the maintenance and surveillance programs, fio deviations or itens of noncompliance were identified.
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Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on October 23, 1980. The scope and
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findings of the inspection were discussed, as presented in paragraph 2 through 8.
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