IR 05000321/1981018
| ML20009G741 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/08/1981 |
| From: | Kellogg R, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20009G734 | List: |
| References | |
| 50-321-81-18, 50-366-81-18, NUDOCS 8108040614 | |
| Download: ML20009G741 (7) | |
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' UNITED STATES ~
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NUCLEAR REGULATORY COMMISSION g
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ATLANTA, GEORGI A 30303
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. Report Nos. 50-321/81-18 and 50-366/81-18 Licensee:: Georgia-Power Company 270 Peachtree Street Atlanta, GA 30303 Facility liame:
Hat'ch 1 and 2 Docket Nos. 50-321 and 50-366 i-License Nos..DPR-57 and NPF-5
l Inspection it Hatch site near Baxley, Georgia
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Inspector:
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R. F. flogers,, Senior Resident Inspector Date Signed
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Approved by:
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Paul J. Kellogg, Acting Chiefi, Reactor Project Date Signed Branch 2, Division of Resident and Reactor
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Project Inspection SUMMARY
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Inspection on May 21 - June N,1981 Areas Inspected L
This inspection involved 92' inspector-hours on site in.the areas of technical
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specification compliance, housekeeping, operator performance, overall plant operations, quality assurance practices, station and corporate management practices, corrective and preventive maintenance activities, site security procedures, radiation control activities, surveillance activities, licensee event reports, NUREG 0737 action items, and previous enforcement items.
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. Resul ts
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Of the 12 areas inspected, no apparent violations or deviations were identified.
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8108040'614 810709':
PDR ADOCK 05000321.
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DETAILS 1.
Persons Contacted Licensee Employees -
- M. Manry, Plant. Manager-
- T. Greene, Assistant Plant Manager S. Baxley, Superintendent of Operations R. Nix, Superintendent of Maintenance C. Coggins, Superintendent of Engineering Services W. Rogers,-Health Physicist C. Belflowar, QA Site Supervisor Other licensee employees contacted included technicians, operators, l
mechanics, security force members, and office personnel.
- Attended exit interview i
2.
Exit Interview The inspection scope and findings were summarized on June 5, and June 21, 1981 with persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection' Findings
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a.
Noncompliance I
(Closed) (321, 366/81-01-01):
Failure to Follow HP Procedures.
The l
licensees corrective actions ha've been adequate.
Followup checks by j
the inspector have verified improvement in HP procedural compliance.
This item is closed.
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(Closed) (366/81-04-01):
Inoperability of the Core Spray System. The applicable procedure was appropriately reused and personnel responsible adequately counselled. This item is closed.
(Closed) (366/81-04-02):
Inadequate Review by the Plant Review Board (PRB).
P"9 members were informed of the nature of the inadequate review to prevent recurrence.
This item is closed.
(Closed) (366/81-03-01):
Control Rod Reed Switch Replacement Documen-
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Licensee procedures (HNP-2-9600) have been revised to prevent
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recurrence.
This item is closed.
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l-(Closed) (366/81-03-03): -Main Steam Isolation Valve Leakage Test Instrument Calibration.
The licensee has obtained properly calibrated
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This item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Plant Operations Review (Units 1 and 2)
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The inspector periodically during the inspection interval reviewed shift I
logs and operations records, including data sheets, instrument traces, and l
records of equipment malfunctions. This review included control room logs and auxiliary logs, operating orders, standing orders, jumper logs and equipment tagout records. The inspector routinely observed operator alertness and demeanor during plant tours.
During normal events, operator performance and response actions were observed and evaluated.
The inspector conducted random off-hours inspections during the reporting interval to assure that operations and security remained at an acceptable level. Shift turnovers were observed to verify that they were conducted in accordance with approved licensee procedures.
Within the areas inspected, no violations or deviations were identified.
6.
Plant Tours (Units 1 and 2)
The inspector conducted plant tours periodically during the inspection i
l interval to verify that monitoring equipment was recording as required, t
equipment was properly tagged. operations personnel were aware of plant
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conditions, and plant housekeeping efforts were adequate.
The inspector also determined that appropriate radiation controls were properly established, critical clean ' areas were being controlled in accordance with procedurcs, excess equipment or material is stored properly and combustible material and debris were disposed or expeditiously.
During tours the inspector looked for the existence of unusual fluid leaks, piping vibrations, pipe hanger and seismic restraint settings, various valve and breaker positions, equipment caution and danger tags and component positions, adequacy of
.re fighting equipment and instrument calibration
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j dates. Some tours were conducted on backshifts.
Within the areas inspected, no violations or deviations were identified.
7.
Technical Specification Compliance (Units 1 and 2)
During this reporting interval, the inspector verified compliance with
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selected limiting conditions for operations (LC0's) and results of selected
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surveillance tests. These verifications were accomplished by direct obser-vation of monitoring instrumentation, valve positions, switch positions, and review of completed logs and records. The licensee's compliance with selected LC0 action statements were reviewed on selected occurrences as they happened.
Within the areas inspected, no violations or deviations were identified.
8.
Physical Protection Units (1 and 2)
The inspector verified by observation and interviews during the reporting -
interval that measures taken to assure the physical protection of the facility met current requirements.
Areas inspected included the organt-zation of the security force, the establishment and maintenance of gates, door and isolation zones in the proper condition, that access control and s
badging was proper, and procedures were followed.
Within the areas inspected, no violations or deviations were identified.
Review of Nonroutine Events Reported by the Licensee (Units 1 and 2)
9.
The following Licensee Event Reports (LERs) were reviewed for potential gencric impact, to detect trends, and to determine whether corrective actions appeared appropriate.
Events _which were reported imediately were also reviewed as they occurred to determine that Technical Specifications were being met and that the public health and safety were of utmost con-sideration. Astericked reports were followed up indepth onsite.
LER No.
Date of Report Description 50-321/81-15 3/31/81 Excessive leakage on LLRTs 50-321/81-16 3/26/81 Inboard MSIVs leakage 50-321/81-17 3/26/81
- ADS relays out of calibration 50-321/81-19 3/27/81
- LPCI relays out of calibration 50-321/81-20 4/7/81 SBLC relief valve lifted low 50-321/81-21 3/26/81,
- SRV clamps broken 5/28/81 50-321/81-22 4/9/81 Purge valves leaking
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50-321/81-23
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- RCIC turbine exhaust valve
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failed LLRT '
50-321/81-24 4/21/81 Nitrogen and feedwater valve l
leakage
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I 50-321/81-27 4/23/81 Feedwater valve leakage
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50-321/81-28 4/23/81
- Fire tank water level low l
50-321/81-29 4/23/81
- Non-seismic pipe supports
50-321/81-30 5/5/81 RPS MG set relay calibration l,,,g 50-321/81-32 5/27/81
- RCIC and CRDs not seismic ii'L!
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!50-321/81-33 5/2i/81
- SRVs found out of calibration
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l 50-321/81-34 4/30/81
- RWCV hanger inadequate
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50-321/81-35 5/21/81 1B D/G inoperative 50-321/81-36 5/27/81
- HPCI exhaust nozzle seismicity 50-321/81-37 5/21/81
- Inadequate charcoal in filter bank l
50-321/81-38 5/13/81 Drain pump discharge valves leaking I
50-366/81-15 3/17/81
- IRM pin failure 50-366/81-16 3/27/81
- DISR separation on MSIV 50-366/81-17 3/26/81
- RCIC trip coil malfunction 50-366/81-20 4/7/81 RHR pressure switch out of calibration
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50-366/81-21 4/9/81
- IRM problems (various)
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50-366/81-22 3/26/81
- 2C D/G fuel oil tank low 50-366/81-23 4/3/81
- Drywell pressure switches iso'ated 50-366/81-24 4/16/81'
Failure of 24/48 volt battery
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charger 50-366/81-25 4/23/81
- Temporary loss of secondary containment 50-366/81-26 4/30/81 Faiure of B SGBT train
50-366/81-27 4/14/81
- Nonconservative !!CPR limit 50-366/81-28 5/5/81
- Battery water levels abnormal 50-366/81-29 5/5/81
- RCIC'inbd steam supply valve I
failure 50-366/81-30 5/5/81 Valve position lights out
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50-366/81-31 4/28/81 RHR switch out of calibration 50-366/81-32 5/5/81
- HPCI aux oil pump trip
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50-366/81-33 4/28/81 Inoperable H2-02 recorder Within the areas inspected, nu violations or deviations were identified.
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10.
NRC Task Action Plant Requirements review (NUREG 0737) (Units 1 and 2)
The inspector has reviewed the licensees implementation of various requirements associated with the NRC Task Action Plan (TAP) in response to the Three Mile Island accident. The current status is summarized below.
Item numbers refer to TAP line items.
NUREG 0737 Item No.
Description Implemen. Date Completed
II.E.4.2.1-4 Implement diverse 1/1/80 Yes isolation II.E.4.2.5.a Specify pressure 1/1/8',
Yes II.E.4.2.6 Purge valves 1/1/81 Yes
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II.E.4.2.8 Technical Specifi-12/15/80 Yes I
cations
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II.K.3.13.a HPCI and RCIC analysis 1/1/81 Yes I
II.K.3.22.a RCIC suction procedures 1/1/81 Yes, III.A.1.2 Interim TSC, OSC, and
- 1/1/81 Yes E0F
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III.D.1.1.1 Primary coolant leak Complete Yes reduction
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- III.D.1.1.2 Technical Specifica-12/15/80 Yes tions
III.D.3.3.1, 2 Inplant radiation
. 1/1/81 Yes
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monitoring
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