IR 05000364/1980035
| ML19339A803 | |
| Person / Time | |
|---|---|
| Site: | Farley |
| Issue date: | 09/30/1980 |
| From: | Gibson A, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19339A802 | List: |
| References | |
| 50-364-80-35, NUDOCS 8011050286 | |
| Download: ML19339A803 (5) | |
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pf jh UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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N REGION 11
g 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
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Report No. 50-364/80-35 Licensee: Alabama Power Company 600 Nerth 18th Street Birminb am, AL 35202 h
Facility Name: Farley Unit 2
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License No. CPPF-86 Inspection at Farley Nucjearpnt near Ashford, Alabama
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Inspector:
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G. L. Tr< u f
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Dite ' Signed T/.38/ fro j
Approved by:
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A. F.' Gibson, Section Chief, FFEJIS Branch Date Signed
" W!ARY
Dates of Inspection September 3-5, 1980 Areas Inspected This routine, announced inspection iru lved 19 inspector-hours onsite in the areas of radiation protection and radioactive waste management including pre-operational and startup test procedures, health physics and effluent procedures, radioactivity monitors, filter systems and previously identified items.
Results Of the six areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- W.
G. Hairston, III, Plant Managar J. D. Woodard, Assistant Plant Manager
- K. W. McCracken, Technical Services Superintendent
- D. E. Mansfield, Startup Superintendent
- C. D. Nesbitt, Chemistry and Health Physics Supervisor
- M. W. Mitchell, Health Physics Sector Supervisor
- J.
M. Waldan, Waste and Effluent Sector Supervisor B. P. Patton, ALARA Ilealth Physicist W. G. Gripentog, Chemistry and HP Foreman
- J. W. Kale, Jr., QA Engineer Other licensee employees contacted included four technicians.
NRC Resident Inspectors
- W. H. Bradford
- J. P. Mulkey
- Attended exit interview 2.
Exit Interview T5.e inspection scope and findings were summarized on September 5, 1980 with those persons indicated in Paragraph I above. The status of preoperational testing and the milestones for completion of outstanding preoperational tests of the liquid radwaste system was also discussed.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items D' resolved items were not identified during this inspection.
5.
Procedures a.
In RII Report 50-364/80-17, open item 80-17-03 was identified relating tc the completion of health physics procedures, specifically FNP-2-R( P-112 and FNP-2-RCP-372. The inspector discussed ~the status of the procedures with licensee representatives and reviewed the procedures applicable to Unit 2.
The two procedures (-112 and -372) have been completed; a licensee representative stated that only the routine
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a-2-O survey pron-dure was outstanding and that it was pending completion of the survey map drawings. After reviewing. the procedures for Unit 2, the inspector stated that he had no further questions concerning health physics procedures and that open item 80-17-03 was closed.
b.
The inspector discussed the status of effluent procedures with licensee representatives. Of thirty surveillance test procedures (STP's) identified, twenty-two have been approved and issued; a licensee representative stated that the remaining eight procedures had been written and were
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in the approval cycle.
Procedure FNP-0-RCP-175, " Schedule, Effluent
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Monitoring and Counting Room Activities" must be. revised to reflect
the Unit 2 Technical Specifications effluent sampling requirements but is pending the final issue of the Technical Specifications.
The inspector had no further questions.
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6.
Radioactivity Monitors The inspector toured the facility and observed the physical installa-a.
tion of airborne radioactivity monitors which are specified in Technical Specifications Tables 3.3-6 and 4.3-9 to be operable in Mode 4 (350 >T)
200*F) or above.
The inspector noted that the monitors are the type
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described.in FSAR Section 11 and are connected to the appropriate process lines.
The inspector also reviewed the records for the calibrations performed in accordance with plant procedures (FNP-0-RCP-XXX series).
The inspector had no further questions on these monitors.
Monitors inspected were:
(1) R11 Containment APO (2) R12 Containment Gas
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(3) R14 Plant Vent Gas l
(4) RIS Condenser Air Ejector (5) R21 Plant Vent APD (6) R22 Plant Vent Gas (7) R24 A, B Containment Purge Open item 80_17-02 remains open pending the completion of the calibra-tion of the Auxiliary Building ventilation monitors.
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b.
The inspector observed the installation of the liquid effluens. monitor (R18) and reviewed the calibration records for - the monitor.
The inspector had no further questions.
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7.
Preoperational Test Procedures a.
Section 14.1 of the FSAR describes the testing program,- including development of the preoperational test program per ' Regulatory Guide 1.68 and review and approval requirements. FSAR Sec' tion.14.1.3 lists
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- the preoperational tests and synopses of the objectives, prerequisites, test :rethods and acceptance criteria.
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b.
The inspector reviewed two preoperational test procedures to determine
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i that they meet the test objectives and criteria of FSAR Section 14.1.3, including the appropriate requirements listed in Appendix C of Regulatory Guide 1.68 and were reviewed and approved as specified ir. FSAR Section 14.1. Procedures reviewed were:
(1) 063-5-006, " Steam Generator Blowdown Spent Resin Processing Preop", Rev. 0 (2) 072-5-004, " Gaseous Radwaste Preop", Rev. O The inspector had no further questions on these procedures.
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8.
Startup Test Procedures I'
a.
Section 14.1 of the FSAR describes the testing program during startup, including procedural requirements and review and approval requirements.
FSAR Table 14.1-3 lists the tests to be performed at low-power and
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j during power ascension, including test objectives and acceptance criteria.
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b.
The inspector reviewed two startup test procedures to determine that
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they meet the objectives and criteria of FSAR Table 14.1-1 and were i
reviewed and approved as specified in FSAR Section 14.1.
Procedures reviewed were:
i (1) 500-7-050, " Radiation Measurements at Steady State Conditions During Power Escalation," Rev. O i
(2) 500-7-542, " Chemical-Radiochemical Analysis", Rev. O In reviewing the procedure for radiation measurements (shield survey)
+he inspector questioned the lack of neutron measurements around
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p'netrations, hatches, etc., and in the Auxiliary Building areas a d,,1 cent to the containment.
These comments were acknowledged 'by licecsee representatives and the procedure was revised prior to submit'.ing for approval. Both procedures were reviewed by PORC and approved by the Plant Manager on September 5.
The inspector had no further questions.
t 9.
HEPA and Charcoal Filter Systems In RII Report No. 50-364/80-18, open item 80-18-01 was identified regarding the removal of fire deluge systems from charcoal filter systems. FSAR Table 6.2-13A states that Section C.3.j of Regulatory Guide 1.52 is applicable; Section C.3.j stated that water sprays to inhibit adsorber
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fires sh<>uld be provided. However, Section 4.4.4.4.4, " Fire Suppression
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Systems for Charcoal Filter" of the "Farley Nuclear Plant Fire Protection Program Reevaluation" states "No fire protection is provided for charcoal filters." The fire protection plan was approved for Unit 1 by license
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Amendment No. Il and was approved for Unit 2 by the same amendment. Based on the approved fire protection program, the inspector informed licensee management that open item 80-18-01 was closed but that FSAR 6.2-13A should be updated; this was acknowledged by licensee management. This will be carried under existing open item 80-18-05.
10.
Previously Identified Items (Open) Area Radiation Monitors (80-17-01). The inspector observed that the instrument boxes for several monitors were installed but the detectors had not been installed and calibrated.
(0 pen) Shielding of Spent Resin Sluice Lines (80-18-04). The inspector observed that the shielding for the sluice lines has not yet been installed.
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