IR 05000348/1981022
| ML20033D073 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/28/1981 |
| From: | Collins T, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20033D068 | List: |
| References | |
| 50-348-81-22, 50-364-81-25, NUDOCS 8112070191 | |
| Download: ML20033D073 (5) | |
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u UNITED STATES B
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NUCLEAR REGULATORY COMMISSION
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e REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 g
ATLANTA, GEORGIA 30303
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Report Nos. 50-348/81-22 and 50-364/81-25 Licensee: Alabama Power Company 600 North 18th Strcet Birmingham, AL 3;291 Facility Name:
Farley Docket Nos. 50-348 and 50-364 License Nos. NPF-2 and NPF-8 Inspection at Farley te near Dothan, Alabama Inspector:
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T.R. Col (fpi I
Date Signed
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Approved by:
C. M. Hose 9', Acting Section Chief D' ate Signed Technical Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on October 5-9, 1981 Areas Inspected This routine, unannounced inspection involved 32 inspector-hours on site in the
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area of radiation protection.
Results Of *.he area inspected
,3 violations or deviations were identified.
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.U 8'112070191 811103
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0 REPORT DETAILS 1.
Persons Contacted Licensee Employees
- W. G. Hairstor,, III, Plant Manager
- J. D. Woodar', Assistant Plant Manager
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- C. D. Nesbitt, Technical Superintendent
- M. W. Mitchell, Health Dhysics Sector Supervisor
- H. M. McClellan, GPE-1
- C. G. Walenga, SAER Engineer J. M. Walden, Waste and Effluent Sector Supervisor B. P. Patton, ALARA health Physicist W. G. Gripentog, Counting Room sector Supervisor E. L. Stevenson, Startup Supervisor NRC Resident Inspectors
- W. H. Bradford Thomas Peebles
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- Attended exit interview 2.
Exit Interview
The inspection scope and findings were summarized on October 9,1981 with i
those persons indicated in paragraph 1 above. The inspector stated to plant management that the qualifications of the newly appointed Chemistry and Health Physics Supervisor (C&HP) appeared to not meet Technical Specifica-tion 6.3.1.
This matter would be left as an unresolved item pending' further evaluation by the NRC. Plant management acknowledged this and stated their position was that the newly appointed ',&HP Supervisor qualifications did meet Technical Specification 6.3.1.
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Licensee Action on Previous Inspection Findings-Not inspected.
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Unresolved Items Unresolved items are matters about which.more information is required to determine whether' they are acceptable or may involve'violationsLor devia-'
tions. New unresolved items identified during this inspection are discussed in paragraph 5.
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Chemistry and Health Physics Supervisor Qualifications Technical Specification 6.3.1 requires that the plant Chemistry and Health
Physics Supervisor (C&HP) shall-meet or exceed the qualifications of -
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Regulatory Guide 1.8, September 1975. The inspector reviewed the qualifica-
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tions of the newly appointed Chemistry and Health Physics Supervisor. Based
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on the -resume provided,- it appeared that the individual did not have five l
years of professional experience in applied radiation protection required by
Regulatory Guide-1.8.
The licensee stated that a more detailed resume would be provided to the NRC. The inspector stated to plant management that this item will remain unresolved until evaluation - of the new resume has 'been
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l completed (348/81-22-01; 364/81-25-01).
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6.
' Health Physics Appraisal Inspector Followup Items a.
(Closed) (OPE) 348/79-42-03, Submission of revised semiannual-effluent release report.
A licensee representa+1ve stated that a computer l
program sof tware problem has been corrected to allow accurate values of f
effluent release data. The inspector concluded that this was suffi-cient and had no further questions, b.
(Closed) (IFI) 348/80-41-01, Criteria for crediting experience.
A licensee representative stated that a maximum of-twelve months of credit will be allowed for Radiation. Detection Man experience ~ toward -
ANSI N18.1 qualification on a 50". basis (one month credit for two months experience).
No credit will be allowed : for the : Nuclear Operative experier.ce. The inspector had no further questions.
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(Closed)- (IFI) 348/80-41-02, : and 348/80-41-03,. Retraining.of Health Physics staff in duties assigned and academic training for_ technicians.
A licensee representative stated-that a 5fto 6 week training course has been conducted for Health Physics. technicians. and retraining courses will be sche'duled at a later date.
The inspector reviewed'the two training _ sessions held previously this year' and had no. further questions, d.
(Closed) (IFI) 348/80-41-04, Technician 0JT.and qualification program.
The inspector reviewed.an 0JT qualification program-developed by the
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licensee and had no further questionn
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(Closed) (IFI) 348/80-41-07,LFormal investigation and documentation of TLD/PD difference. A licensee representative stated - t..atutnel TLD/PD
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' differences are now documented-as1 required by Administrative Procedure
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FNP_-0-RCP-8 and the report sent to..the: ALARA Health Physicist :for-
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review and. recommendation for 1nvestigations.
The inspecto'r had no
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further questions.
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(Closed) (IFI) 348/80-41-08, Neutron exposure procedure. A licensee representative stated that the neutron exposure procedure FNP-0-RCP-8
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was revised to eliminate the neutron film badge requirement and the inspector had no further questions.
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(Closed) (IFI) 348/80-41-09, Beta dose through respirator lens. A licensee representative stated that personnel required to wear full face respirators for protection against airborne activity, as well as beta exposure to the eyes, while working inside steam generators will also wear a second lexan shield to give further protection against beta exposure to the eyes. The inspector had no further questions.
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(Closed) (IFI) 348/80-41-23, Safety evaluation of new solidification system. The inspector reviewed a safety evaluation completed by the r
licensee of the new dimineralizer solidification system and had no further questions, i.
(Closed) (IFI) 348/80-41-24, Wr.ste reduction training for plant personnel. A licensee representative stated that radwaste reduction i
training has been incorporated into the General Employee Training (GET)
for radiation workers. The inspector had no further questions.
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(Closed) (IFI) 348/80-41-25, Isolation of dry waste compactor.
The present waste compactor is located on Unit I and an Operation Change Request (OCR) has been issued to move the compactor to. Unit 2.
.A licensee representative stated this will be done at a later date. The inspector reviewed the new location for the waste compactor and had no t
further questions.
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(Closed)(IFI) 364/80-44-03, Testing of post TMI sampling system. The-l inspector discussed this with licensee personnel and concluded the
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sampling system has been tested. and functions properly. Personnel have
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l been trained in the proper operation of the sampling _ system and the inspector had no further questions.
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(Closed) (IFI) 364/80-47-01,. Complete radiation monitoring syst'em pre-op after turnover of detectors R3 and R9.. The~. inspector reviewed the pre-operational testing of both-R3. and R9 - radiation monitors, Phase 1 Test Procedure,- No. 079-3-002,: Westinghouse Radiation.
Monitoring System, Check and Functional Test (C&FT). The inspector had no further questions.
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Radiation Measurements at Steady State Conditions During Power' Escalation of.
Unit 2 Start-up The inspector reviewed the Alabama - Power Company, Farley Nuclear Plant, Unit 2, Phase III Test Procedure 500-7-050, Radiation' Measurements. at Steady.
. State Conditions During-Power Escalation at 0-5%, 5-50%,150-100%, and 100%'
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power levels to determine that the design shielding is adequate for safe plant operation and to keep personnel radiation exposures ALARA.
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inspector had no further questions.
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Posting, Labeling and Control The inspector toured both Units I and 2 auxiliary buildings to ensure proper posting and labelling of contamination areas,. radic4ct be material areas,
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radiation areas and high radiation areas. The inscector determined that the posting and labelling was adequate, although the catrance to the Volume Control Tank room elevation 121 of the auxiliary building on Unit 2, posted as a high radiation area was found unlocked. Radiation levels in this room were less than 1,000 mrem /hr.
Therefore, the room was not required to be locked.by Technical Specifications. This item was preef ously addressed ir.
NRC Region II Report No. 50-348/80-41 item number IFI (348/80-41-17) Control of locked high radiation areas.
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Review of Abnormal Radiation Exposure Recorded Eberline TLD The inspector was informed by the licensee that an abnormal radiation exposure had been recorded on a TLD badge for the month of August 1981.
Upon review of the Eberline Exposure Report on September 18, 1981, by the.
licensee, a radiation exposure was recorded for the individual of 165 mrem whole body gamma and 16,846 mrem skin beta. Allowable limits as stated in 10 CFR 20.101 per calendar quarter for the skin of the whole body is 7,500 i
mrem. In response to this abnormal reading, the licensee began an immediate investigation to determine 'the cause of this high beta radiation exposure reading.
The investigation completed by the licensee concluded that the abnormal beta
radiation exposure was an erroneous reading and that a overexposure did not occur. The inspector agrees with the licensee that'a creditable.whole body and skin exposure of 165 mrem. should be assigned the ~ individual for the
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month of August 1981.
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