IR 05000321/1980001
| ML19309C597 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/05/1980 |
| From: | Moon B, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309C587 | List: |
| References | |
| 50-321-80-01, 50-321-80-1, 50-366-80-01, 50-366-80-1, NUDOCS 8004090049 | |
| Download: ML19309C597 (6) | |
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UNITED STATES 8,
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101 MARIETTA ST N.W., SUITE 3100 NUCLEAR REGULATORY COMMISS!ON
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ATLANTA. GEORGIA 30303
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Report Nos. 50-321/80-01 and 50-366/80-01 J.icensee: Georgia Power Company 270 Peachtree Street Atlanta, Georgia 30303 Facility: Hatch Docket Nos.
50-321 and 50-366 License Nos.
Inspection at liatch site near Baxley, Georgia k
by pM 8D Inspectot-
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B. T. ?!oon f
Daf.e S'igned
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Approved by:_
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hO CT M. Upriy,
,' Ac * g Section Chief,
[ ate [ Signed RONS Branch SU? DIARY Inspection on January 8-11, 1980 Areas Inspected This routine, unannounced inspection involved 26 inspector-hours on site in the areas of calibration of in-plant instrumentation required by technical specifica-tions; calibration of measuring and test equipment used on safety-related systems; and surveillance of in plant equipment required by technical specifications.
Results Of the three areas inspected, no apparent items of noncompliance or deviations were identified in two areas; one apparent item of noncompliance was found in one area (Deficiency-Failure to follow surveillance test procedures paragraph 6.a).
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DETAILS 1.
Persons Contacted Licensee Employees
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- M. Manry, Plant Manager
- T. R. Collins, Laboratory Supervisor
- H. W. Dyer, Operations Supervisor
- G.
B. Ellis, I&C Supervisor
- T.
Greene, Assistant Plant Manager
- C.
E. Belflower, QA Site Supervisor
- D. Smith, Laboratory Supervisor
- G. E. Spell, Jr., Senior QA Field Representative
- C.
L. Goggin, Superintendent, Engineering Services
- C R. Miles, Jr., QA Field Supervisor Other licensee employees contacted included technicians, operators, mechanics and office personnel.
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NRC Resident Inspector
- R. F. Rogers
- Attended Exit Interview 2.
Exit Interview The inspection scope and findings were summarized on January 11, 1980, with those persons indicated in paragraph I above. The noncompliance item discussed in paragraph 6.a was acknowledged by the licensee. With regard to the items discussed in paragraphs 5 and 6, the licensee committed to (1)
review the surveillance procedure (HNP-2-3752M) to upgrade the acceptance criteria by 2/1/80 and (2) review the shop control procedures (RNP-807 and 826) to improve the technical contents by 1/30/80. The licensee also committed to insure that all the required verifications in surveillance data sheets are initialed / signed by performers upon completion of tests.
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3.
Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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5.
Calibration The inspector conducted a review of the calibration procedures and results as follows:
IINP-1-3006, MSIV Closure Instrument FT&C
!!NP-1-3101, Reactor Water Level Instrument FT&C
HNP-1-3111, Main Steam Line Isolation Valve Trip Test
!!NP-1-3151, LPCI Pump Discharge Pressure Interlock Instrument FT llNP-1-5001, SRM Calibration llNP-1-5100, Logarithmic Radiation Monitor-Main Steam Line IINP-1-5108, Logarithmic Radiation Monitor-Post LOCA IINP-1-9017, Reactivity Anomaly Calculation The inspector monitored, on 1/9/80, the performance of portions of calibra-tion conducted in accordance with HNP-1-5202, Burton Model 228A and 389A Differential Pressure Switch Record.
The calibrations above were reviewed to verify:
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Reviews and app ovals were being conducted, and data was recorded and evaluated.
Test instruments were listed and identified in test results.
Adherence to required technical specifications and limiting conditions for operation.
Technical contents of the procedure were correct.
Verification of return of equipment to service and removal of test equipment was accomplished.
The inspector conducted an inspection of instrument test shop, maintenance shop, and chemistry laboratory. The facilities were inspected to verify:
That standard test instruments were labeled and included in the calibra-tion program.
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Instruments were being calibrated on schedule and labeled with calibra-tion status.
Storage facilities were proper for protecting the equipment.
Certification and calibration records were available and being maintained for test equipment.
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The inspector used one or more of the following acceptance criteria for evaluating the above items in the calibration program:
Technical Specifications
E. I. Hatch Plant Quality Assurance Manual, Section 12 - Control of Measuring and Test Equipment.
ANSI N18.7 (1976), Administrative Controls for Nuclear Power Plants.
Within the areas inspected, no items of noncompliance or deviations were identified. The following item remains to be followed up by NRC at subsequent inspections upon corrective action by the licensee: During the inspection of instrument test and maintenance shop, the inspector found that HNP-807, Control of Test Shop Instrumentation, and HNP-826,
Maintenance Shop Measuring and Test Equipment Control, do not include the procedure for " Calibration Frequency", which is required by section 12.2.A of E. I. Hatch Nuclear Plant Quality Assurance Manual (HNPQAM). The manual requires a written procedure describing the calibration frequency of all
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measuring and test instruments (and tools) which are to be used in the measurement, inspection, and monitoring of safety related components, systems and structures. The licensee had lists of tools and instruments which describes calibration frequencies in formats not approved by the plant safety review board. Furthe rmore, there was no procedure describing (1) a format in which the required calibration frequencies are assigned and (2) responsible personnel under whom the formats are maintained and updated.
Yhe inspector stated that the licensee should have a procedure which inplements the requirement of HNPQAM by specifying an approved format as
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well as a delineation of responsibilities under which calibration intervals art established, maintained, and updated.
The ricensee agreed to revise and update HNP-807 and RNP-826 by 1/30/80 (321/t0-01-01, 366/80-01-01).
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6.
Surveillance Test Procedure and Results Verification The inspector conducted a review of the following surveillance procedures
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and results:
HNP-2-3001, RPS High Reactor Pressure Instrument Functional Test HNP-2-3003, Reactor Water Level HNP-1-3161, Recirculation Pump Discharge Operability HNP-1-3162, RHR Valve Operability HNP-2-3185, Verification That All Drywell/ Torus Equipment Hatches Are Closed And Sealed.
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HNP-1-3303, HPCI Pump Rated Flow
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HNP-1-3351, Fire Pump Test HNP-1-3358, Fire Protection Isolation Va}ves Surveillance HNP-1-3752, Battery Individual Cell Surveillance HNP-1-3801, Diesel Generator Manual Start HNP-1-3977, Fuel Pool Cooling System Valves HNP-1-9203, TIP Normalization HNP-1-9402, Scram Insertion Timing
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-4-u The inspector monitored, on 1/9/80, the performance of portions of surveil-lance testing conducted in accordance with HNP-1-3055M, RBM Instrument FT&C, and HNP-1-3410, RCIC Steam Line Delta P Instrument FT&C.
The test procedures and test results were reviewed to verify:
That test prerequisites and' plant conditions were specified and
reviewed, and approvals had been performed; That contents of the procedures were correct and the tests were performed on schedule; That test instruments were listed in the procedures and instruments used were identified in the results; That test results were recorded and compared with acceptance criteria; and, The return of the system / equipment to service and removal of test equipment was verified upon completion of the test.
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The inspector used one or more of the following acceptance criteria for the above items:
Technical Specification, Section 6.8.
E. I. Hatch Nuclear Plant Quality Assurance Manual, Section 11-Test Control.
ANSI N18.7(1976), Administrative Controls for Nuclear Power Plants.
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Industry Practice.
Within the areas inspected, on apparent item of noncompliance and two inspector follow-up items were identified as follows:
a.
During the review of HNP-1-3351-E and HNP-2-9203, the inspector found that certain activities were not followed in accordance with the
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instructions of the procedure. For instance, (1) Step J.3 of HNP-1-3351-E, Fire Pump Test, requires fuel levels of fire pumps 2 and 3 (FP-2 & FP-3) be recorded on the data sheet I as a system restoration. This requirement applies for both " Auto Start" and " Manual Start" tests, according to the instructions described in sections F and G of the procedure. The inspector found that the licensee failed to record the fuel levels on the data sheet five times for " Auto Start" test and one time.for
" Manual Start" test, which were performed on 2/15/79, 6/26/79, 8/14/79, 9/17/79, 10/8/79 and 7/29/79, respectively. The inspector also found that the licensee had an operating procedure by which the fuel level was regularly checked and maintained.
This failure to follow the required step of the procedure was an item of noncompliance and applicable to Unit 1.
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-5-e (2) Section D of HNP-831, Technical Specifications Surveillance Program, requires that a surveillance shall be performed by a respective department in accordance with the requirement assigned in the' assignment sheet (Figure 1) which specifies procedure number and technical specification reference. The assignment sheet is generated on a weekly basis by a surveillance coordinator
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in accordance with the schedules listed in the master computer list. The inspector found during the review of HNP-2-9203, TIP Normalization, sampled between 1/1/79 and 12/31/79 that the procedure had never been used for the monthly surveillance, although it was assigned by the surveillance coordinator.
Instead, another procedure was used to satisfy the requirement by the performer without informing the surveillance coordinator of the changes. The other procedure utilized a computer code which was applicable for the surveillance requirement in the insDector's opinion. However, the licensee was informed that the failure to follow their administrative instructions (KNP-831) in terms of assignments and communications for the entire year was an item of noncompliance and applicable for Unit 2.
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Technical Specification 6.8.1.c requires written procedures be implement-d, covering the activities concerning surveillance and test of safety related equipment. Contrary to the above step J.3 of HNP-1-3351-E was not followed a total of six different times for Unit I and instructions of HNP-2-9203 were not followed throughout the year of 1979 for Unit 2.
This is an item of noncompliance (321/80-01-02, 366/80-01-02);
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During the review of HNP-2-3752M, Battery Individual Cell Surveillance, the inspector found that battery electrolyte level check requirement was not incorporated in the Unit 2 data sheet as an acceptance criteria.
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The inspector stated that the verification of electrolyte level of each cell should be included in the Unit 2 data sheet. The licensee agreed to revise the procedure by 2/1/79(366/80-01-03);
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During the review of Unit I surveillance test completed, the inspector c.
identified that numerous initials as well as a completion date were
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omitted in the data sheets of the procedure listed below and that these errors were not identified during the licensee's review process.
The errors included (1) omitting initials on the battery level check verification (HNP-1-3752H) which was performed on 6/28/79, (2) omitting initials for verification of MSIV valve restoration (HNP-1-3006) which
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was performed on 3/3/79, 9/16/79 and 8/13/79, and (3) not recording a test completion date for HNP-1-3801, Diesel Generator Manual Start, which was performed on 6/5/79.
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The licensee agreed to correct this typetof inadequate review problem in the future and the item will be followed up by NRC inspections (321/ 80-01-03).
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