IR 05000344/1987006
| ML20206E918 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/26/1987 |
| From: | Hooker C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20206E913 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 50-344-87-06, 50-344-87-6, GL-85-08, GL-85-8, IEIN-86-090, IEIN-86-103, IEIN-86-107, IEIN-86-90, IEIN-87-003, IEIN-87-007, IEIN-87-3, IEIN-87-7, NUDOCS 8704130784 | |
| Download: ML20206E918 (8) | |
Text
{{#Wiki_filter:- - , . , , ' , U. S. NUCLEAR REGU'LATORY COMMISSION
REGION V
Report No. 50-344/87-06 . 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 Conducted: March 9-13, 1987 Inspector: N 3,,25'[[ C. A. Hooker, Radiation. Specialist Date ' Signed Approved by: [M du b 3/26/ae/ G. P. Yuh s, Chief . Date Signed . Faciliti Radiological Protection-Section
' Summary: , , - Inspection on March 9-13, 1987 (Report No. 50-344/87-06) ] Areas Inspected: Routine, unannounced inspection of licensee action on.
previous inspection findings, solid radioactive waste, preparations and training for refueling outage, followup.on IE Information Notices, followup on Generic Letter and facility tour.
Inspection procedures addressed included 30703, 84722, 83723, 83729, 92701, 92702 and 92703.
Results: No violations or deviations were identifiedt n the areas inspected.
i , e 8704130784 B70326 PDR ADOCK 05000344 G PDR ,
. . , [ DETAILS 1.
Persons Contacted - , a.
Portland General Electric Company (PGE) Personnel
- R. P. Schmitt, Manager, Operations'and Maintenance D. R. Keuter, Manager, Technical Services-
- C. H. Brown, Branch Manager,- Quality Assurance (QA) Operations
- P. A. Morton, Acting Manager, Technical Services
- N. C. Dyer, Manager, Radiological Services Branch, NSRD
- T. O. Meek, Supervisor, Radiation Protection (RP)
L. D. Larson, Supervisor, Radwaste (RW)
- A. R. Ankrum, On-site Regulation Engineer
- D. O. Leslie, QA Engineer J. C. Wiles, Unit Supervisor, RP J. G. Bailey, Chemistry and RP Training Specialist C. A. Sprain, Acting Supervisor, Chemistry b.
NRC Resident Inspector G. Y. Suh, Resident Inspector In addition to the individuals identified above, the inspector met and held discussions with other members of the licensee's staff.
- Denotes those present at the exit interview on March, 13, 1987.
2.
Licensee Actions on Previous Findings (Closed) Violation (50-344/86-46-02): Violation concerning the failure of an individual to comply with_a requirement, to wear a lab coat while taking samples in the hot sample sink, as specified on a Radiation Work Permit (RWP). The inspector verified that the licensee's response to the subject violation, as identified in PGE letter dated February 6, 1987, was timely and corrective action had been implemented as determined through discussions with cognizant licensee representatives, and observations made during the inspection.
In review of RWP No. 87-21, Routine Chemistry, the inspector noted that the requirement to wear a lab coat during sampling of the Treated Waste Monitoring Tanks (TWMTs) had been lined out and initialed by the RP unit supervisor.
The RP unit supervisor informed the inspector that due to the low radioactivity level of the TWMT samples and with no known personnel contaminations from the operation, the use of lab coats was' determined to be unnecessary.
The inspector acknowledged the fact that the TWMTs were not very highly radioactive;however,thecontaminationlevelsins{deofthehooded sample sink ranged from 4,500 to 16,000 dpm/100 cm according to the licensee's routine survey on March 10, 1987, due_to various primary system samples obtained in the same sample hood. _The inspector noted that reducing the protective clothing requirements for this operation (sampling of TWMTs) within a contaminated environment, represents a double standard compared to RP practices.normally imposed at the _ F-
, ,
, facility.
This matter was also. discussed at the exit interview on March 13,-.1987, and the licensee acknowledged the inspector's concern.
The licensee informed the inspector that this matter would be reevaluated.
. Closed) Followup (50-344/83-33-01): Inspection Report Nos.
( 50-344/83-33, 50-344/85-09, 50-344/86-18, and 50-344/86-46 documented previous inspection efforts regarding the licensee's need and efforts to evaluate sample line losses for air particulates and radioiodines for process and effluent monitoring systems (PERMS) 1 and 2.
Based on review of the licensee's analysis, Calculation Report No. 86-46, that was performed using the analytical methodology outlined in American National Standard 13.1-1969, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, the inspector determined that the licensee has adequately demonstrated that particulate plate-out is negligible.
In regard to radioiodine, the licensee has taken the necessary step to ensure heat tracing will be provided for PERMS 1 and 2.
Both, the analysis for particulate plateout and heat tracing for radiciodines satisfies the criteria of Item II.F.1, Attachment 2, Sampling and Analysis of Plant Effluents, to NUREG 0737.
(Closed) Followup (50-344/86-46-01): Inspection report described the inspector's review of the licensee's internal Event Report (ER) No.
86-122 regarding TWMT volume discrepancies, and the need for the licensee to reevaluate the matter.
Through discussions with licensee representatives this inspector was informed that the matter had been reevaluated and an error did exist in previous radioactive liquid discharge volumes recorded.
The new tank volume curves are now consistent with calibrations of tank volumes based on instrument reference points.
The licensee informed the inspector that the error would be reported in the July 1 through December 31, 1986, semiannual effluent report.
The inspector was also informed that the value (10%) being reported in the semiannual effluent report was also in error (typographical) and a corrected value (.20%) would be submitted at a later time.
The inspector considers the matter concerning reevaluation of tank volume discrepancies closed. _ The inspector will review the licensee's submittal of corrections to the semiannual effluent report (50-344/87-06-01,Open).
3.
Solid Wastes The inspector reviewed the licensee's radioactive solid waste program for compliance with the requirements of 10 CFR. Parts 20, 61 and TS.
a.
QA Audits and Surveillances QA Audit No. 468, Report No. CAO-539-86, was examined. The audit was conducted December 5-11, 1986.
The scope of the audit included the areas of:
Radwaste Organization and Management Performance Monitoring Personnel Qualifications and Training
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Plant Operating Manual Implementation . Trojan TS The audit concluded that the overall handling, classifying, packaging, labeling, marking, placarding, surveying and shipping-requirements of the NRC and_ DOT had been effectively implemented.
As a result of the audit six recommendations and five Nonconforming Activity Reports (NCARs) were identified.
The audit was noted to be extensive, and utilized three QA auditors.
Inspection Report No.
50-344/86-46 documented the inspector's observations during the QA exit interview regarding this audit.
During this inspection the- ' inspector focused on the responses to the NCARs, which were primarily administrative in nature.
Based on review of documented
corrective actions taken with respect to the NCARs and discussions ' with cognizant licensee representatives the inspector had no further questions.
' QA Surveillance Report No. P131 was also examined.
The surveillance was conducted March 4-6, 1987, during a steam generator ion exchange dewatering process that included observations of:
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Dewatering connections to the resin liners i
Sluicing of resins to liners l ! Dewatering of resin liners -
RP activities
No deficiencies were identified during this QA surveillance.
The ' surveillance appeared extensive and well detailed.
No violations or deviations were identified.
' b.
Changes ! The licensee had made several changes to existing procedures.and had implemented five new procedures for program improvement.
New procedures are indicated as follows:~ . .
RPMP-2-2 Drumming Powder Resin Waste RPMP-2-3 Packaging Dry Radioactive Waste in Liners,
RPMP-2-4 Packaging low-Level Dewatered Resins in Liners ! (Class A - LSA Waste Only) ,
RPM-2-5 Packaging Dry Radioactive Waste in Boxes ,
RPM-2-8 Radwaste Drumming - Absorbed Lubricating Oils Using Petroset II T - - ._ -. - -
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. Based on review of procedural changes'and new procedures it appears that the licensee has taken a positive approach to document important operations to enhance quality in the solid RW program.
The inspector also noted that the licensee was undergoing a preliminary design review for modifications to the steam generator blowdown system (SGBS) and liquid radwaste system (LRS).
The SGBS components from the in-board containment isolation valves of the steam generator blowdown lines to the point of blowdown effluent, excluding SGBS ion exchangers will be redesigned.
The LRS portion of this change involves.the addition of ion exchangers dedicated to i RW services.
The SGBS fon exchangers will be used for blowdown service as originally designed.
No violations or deviations were identified, c.
Processing ' The licensee plans on continuing the use of a contract vendor for solidification and/or dewatering of spent resins for high activity wastes.
No high activity waste processing has taken place since those noted in Inspection Report No. 50-344/86-30.
The licensee contracts with an offsite vendor for identification of.
radionuclide concentrations in appropriate waste streams.
The licensee also samples and has analysis performed during each process operation from the spent resin storage tanks.
The inspector toured the licensee's waste processing and storage facilities and observed waste separation and compaction areas.
No items of concern were identified.
, In addition to the new procedures noted above, the following procedures and documents were also examined.
RPMP-4 Determination of Radioactive Material Shipping and Waste Classification e '
RPMP-2 Routine Packaging of Radioactive Waste RPHP-2-1 Drumming and Compacting Dry Radioactive Waste RPMP-2-6 Absorbing Radioactive Liquid for Burial RPMP-2-7 Determination of Liquid / Absorbent Ratio RPMP-5 Sampling Program to Determine Isotopic Concentration and Scaling Factors for Classification of Low-Level Solid Radwaste i Radioactive Waste Shipments Nos. 87-4, 87-2 and 87-1 Based on the reviews and observations made during this inspection, the inspector determined that the licensee classifies waste pursuant to 10
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CFR 61.55; verifies that waste meets the characteristics of 10 CFR 61.56; and prepares a waste manifest and marks packages in accordance with 10 CFR Part 20.311.
No violations or deviations were identified.
4.
Preparations for Refueling Outage and Training a.
Refueling Outage The inspector discussed licensee's preparat*ons and plans for the , l upcoming refueling outage, scheduled to start in the first week of April 1987, with cognizant RP and Chemistry personnel.
The licensee is contracting for 62 Senior and 28 Junior RP Technicians, and 24 Waste Handlers to augment the current staff, b.
Contract RP and General Employee Training (GET) The inspector was informed that the contract Senior RP Technicians are being required to meet the training and qualifications outlined in ANSI N18.1-1971, in accordance with TS 6.3.1.
Junior RP Technicians and Waste Handlers would be utilized in the areas in which they were experienced.
In addition to GET, contract j technicians were being trained on appropriate licensee procedures and given written exams to test their knowledge and skills.
The inspector reviewed six exams of selected contract staff.
No concerns were noted with the licensee's testing.
The RP unit supervisor informed the inspector that he was personally contacting previous employers regarding performance and job capabilities of contract workers whom the licensee was not familiar with, l The inspector also attended and observed GET refresher training ' being provided to various contract and professional staff.
In addition to classroom instruction, the licensee evaluated each workers' ability to use protective clothing.
Based on observations in this area, the inspector determined that the licensee's GET program met the requirements of 10 CFR 19.12 and generally followed the guidelines recommended in Regulatory Guides 8.27 and 8.29.
c.
Self Contained Breathing Apparatus (SCBA) - Emergency Teams NRC Inspection Report No. 50-344/86-41 identified a problem regarding the use of SCBAs during the licensee's November 19, 1986, emergency preparedness exercise.
It was noted during this exercise, in the Operations Support Center, that 14 out of 15 individuals (engineering and maintenance) experienced significant problems in the ability to use SCBAs.
These indivic.uals were purportedly qualified.
During this inspection, the inspector reviewed the licensee's corrective actions in regard to this matter.
Based on discussions with cognizant licensee representatives, the following l observations were made:
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.- (1) Prior to the exercise, annual training on the use of SCBAs had been the responsibility of each department's supervisor ' (engineering and maintenance).
It appeared that this training mainly consisted of individuals observing a video tape and a demonstration on the use of the SCBAs.
The inspector was informed that actual hands on training was probably not being conducted.
From discussions with licensee representatives it also appeared that audits were not conducted to determine the-effectiveness of this specific type of training.
, (2) Since the exercise, retraining of the individuals in the area of concern has been provided by the licensee's training department.
The licensee had retrained 110 individuals and had 20 more scheduled.
The licensee expects to have all involved i personnel retrained by their upcoming remedial exercise on ' March 26, 1987.
(3) The licensee plans to develop a more formalized refresher ) training program after the remedial exercise.
The refresher training will include more hands on training and will be evaluated, by a program evaluator.
No violations or deviations were identified.
5.
Followup on IE Information Notices The inspector verified that the licensee had received, reviewed and was taking or had taken action on IE Information Notices Nos. 86-90, 86-103, 86-107, 87-03 and 87-07.
No violations or deviations were identified.
6.
Followup on Generic Letter Based on discussions with a corporate licensee representative, the inspector determined that the licensee had incorporated the recommendations provided in Revised NRC Form 439, Report of Terminating Individuals' Occupational Exposure, dated July 1, 1986, in reference to Generic Letter No. 85-08, 10 CFR 20.408 Termination Reports - Format, dated May 23, 1985.
The licensee had requested a waiver from the 30/90 day time limit for reporting terminations to the NRC, letter dated February 21, 1986, which stated, in part, that all 10 CFR 20.408 termination data, after January 1, 1987, would be electronically transmitted to the NRC in batches on a time frequency not to exceed six months.
The licensee has discussed this matter with the Office of Nuclear Reactor Regulation (NRR); however, as to date NRR has not responded.
l No violations or deviations were identified.
7.
Facility Tour The inspector toured various areas of the auxiliary building, fuel handling building and waste handling annex.
The inspector made
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, _- c .; + . - . ,, . > y - . c , , independent measurements with NRC R0-2 portable i$n' chamber, ShN 837,- due "
for calibration on May.23,.1987.,
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-> ' The inspector observed that'all radiation, areas and high' radiatiori areas were posted as required-by 10-CFR Part 20, and access. controls were consistent with TS 6.12 and licens~ee procedures.
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Theinspector.alsonoted,ni$contaminationareas,Lthat'workerswere properly suited in protective' clothing and equipped with appropriate personnel monitoring. devices.- Housekeeping.was,also noted to'be - generally good.
. No violations or deviations were identified.
. . 8.
/ Exit ~ Interview ~ + ' ' The inspector met with thi licensee representatives _(denoted in paragraph ^1) at the conclusion of the inspection on March 13, 1987. -The scope and' findings of the inspection were-summarized. The licensee was _ . informed that no violations or deviations were, identified.
With respect to deleting the requirement-to wear a lab coat while sampling the TWMTs as described.in paragraph 2.of this report, the-licensee acknowledged the inspector's concern.
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