IR 05000244/1981001
| ML17258B107 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/25/1981 |
| From: | Blumberg N, Greenman E, Shaub E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17258B106 | List: |
| References | |
| 50-244-81-01, 50-244-81-1, NUDOCS 8106120077 | |
| Download: ML17258B107 (34) | |
Text
U.S.
NUCLEAR 'REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-244/81-01 Docket No.
50-244 License No.
DPR-18 Priority.
Licensee:
'ochester Gas 8 Electric Cor oration Category 89 East Avenue Rochester, New York 14649 Facility Name R.
E. Ginna Nuclear Power Station Inspection at:
Ontario, New York Inspection conducted:
January 12-16, 1981 Inspectors:
'I N. J.
Blu berg,'!Reactor nspector date signed E. T. Shaub, Reactor Inspector d te igned
. Approved by:
E.
G.
Gree a, 'Chief, Rea tor Operations and Nuclear Support Section 0'2 date signed
~/ei ate igned Ins ection Summar:
Ins ection on Januar 12-16, 1981 Re ort No. 50-244 81-01)
~1I: I;,
d; d
by g-b d I d I I
followup on previously identified inspection findings; administrative controls for safety related maintenance; implementation of safety-related maintenance; adequacy of safety related maintenance program; adequacy of housekeeping and cleanliness program; administrative controls for facility procedures; facility procedures, standing orders, checklists and related forms and changes hereto for conformance to administrative controls and Technical Specification require-ments and for technical adequacy; compliance to recent license amendments and to ensure incorporation into facility procedures, where applicable; verification that procedural changes were in conformance to
CFR 50.59(a)
and (b) requirements; Control Room observations; and a facility tour.
The inspection involved 66 inspector hours onsite by two region-based inspectors.
~
~
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Results:
Noncompliances:
None in ten areas and one in one area (Violation - Failure to establish procedures for control of plant housekeeping and cleanliness
- para-graph 6.b).
Region I Form l2 (Rev. April 77)
8106y2 Oa lg
~
i
DETAILS Persons Contacted
- W. Backus, Operations Supervisor
~J.
Bodine, Quality Control Engineer R. Brown,. Procedures Coordinator G. Cain, Assistant I&C Foreman B. Leimberger, Maintenance Aide A. McNamara, Operations Aide G. Meier, Assistant Training Coordinator K. Nassauer, Quality Control Technician
"J.
Noon, Assistant Station Superintendent T. Rakewicz, I&C Foreman
- M. Sitaw, Quality Control Technician
~B.
Snow, Station Superintendent
~S. Spector, Maintenance Engineer J.
Wahl, Mechanical Foreman
.
B. Yeckel, Shift Supervisor USNRC
"R. Zimmerman, Senior Resident Reactor Inspector The inspectors also interviewed other licensee employees during the inspec-tion, including reactor operators, technical support, administrative and clerical personnel.
Licensee Action on Previous Ins ection Findin s
(Closed)
Unresolved Item (244/78-18-02):
Several hundred Ginna Station Work Order and Trouble Reports (TR's) were outstanding with some dating back to 1973.
The licensee had stated that a comprehensive review of the Work Order and Trouble Report system would be completed to (1) evaluate and reassign priority to close important items,.and (2) the file updated to assure it reflects an accurate completion status.
The inspector determined that approximately 200 TR's remain outstanding.
Most date from 1977; however two or three date back to 1974.
Discussions with the Maintenan'ce Engineer.indicated that these items were of a low 'priority or required modifications which had a low priority.
A random inspection of outstanding items did not indicate any that were safety significant.
Additionally, Procedure A-1603, Maintenance Work Order.and Trouble Report, has been revised to assign priorities to safety related maintenance.
Based on the above, the inspector determined that this item should be closed, and that incomplete maintenance for safety related components that are noted during future inspections should be reviewed and evaluated on a case by case basi '3 (Closed)
Inspector Follow-up Item (244/79-06-01):
Failure to achieve. motor break away at 300 Ft-Lbs on RCP motor indicated a possible lube oil leak.
Licensee investigation found a leak in lube oil lift system; however, the licensee had not yet performed a review regarding the cause of,the line failure, and a determination of whether further corrective actions were appropriate.
The cause of the problem was determined by a Westinghouse Information Bulletin to be the inadequate strength of the copper tubing in use.
The Bulletin recommended that copper tubing be changed with stainless steel tubing.
The inspector verified that maintenance procedure M11.8.J was revised to include the replacement of the copper lube oil lines with stainless steel and that the copper tubing was replaced with stainless steel tubing for both pumps.
(Closed)
Inspector Follow Item (244/79-08-06):
Oetai led return to service procedures are not provided in maintenance procedures and calibration procedures.
The inspector observed that maintenance procedures now include step-by-step return to service instructions or the system/component was turned over to the Results and Test Group to perform required surveillance (periodic tests)
which included detailed step-by-step return to service instructions.
(Closed)
Unresolved Item (244/79-SP-01):
Cast iron yokes installed on pressurizer power operated relief valves (PORV's) were subject to failure.
Plant operations were continued with PORV blocking valves shut until the yokes could be replaced.
Inspection 79-19 determined that the valves were maintained closed using the plants holding (tag-out)
procedure but that appropriate operating procedures had not been revised to assure the blocking valves were closed during plant operation.
Records of -the holding action could not be produced prior to the end of the inspection.
On Oecember 21, 1979 the plant notified NRC:Region I that holding action records had been located and that appropriate procedures had been revised.
The inspector reviewed records of the holding procedure used and revised emergency pro-cedures El.2, E1.3 and E1.5.
In addition, the inspector reviewed the minutes of the Oecember 26, 1979 PORC meeting that reviewed and discussed a
letter from K. Amish to V. Stello dated October 5, 1979.
This letter discussed the plant design basis review performed to determine if the PORY's are required for any design bases event, or a failure of one or both PORV's, either as a single event or a consequence of another transient has been analyzed.
The only design bases event for which the PORV's are assumed to function is a low temperature overpressure event, and the fai lure of the PORV's has been analyzed and shown to have acceptable consequences (RESAR 3,
Amendment 1, pp. 15.3.8, 8a and 9).
The inspector had no questions concerninq the licensee's evaluation.
The PORV's have subsequently been replaced which eliminates the need to operate with the PORY blocking valves closed.
The holding action has been removed and procedures revised again to reflect that the PORV's are operationa v ~ '
(Closed)
Unresolved Item (244/79-19-03):
Plant Operation Review Committee
,.(PORC) minutes were reviewed to determine if the Powel Operated Relief Valv'e (PORV) cast, iron yoke problem had been formally reviewed and documented by the PORC.
Because of time limitations during inspection 79-19, this PORC review could not be located although the licensee stated such a review had been accomplished.
The PORC Minutes have been located and the inspector determined that PORC Minutes dated December 26, 1979 documented formal'eview, including a letter to V. Stello from K. Amish, and a recommendation to operate with the PORV blocking valves closed during power operations.
(Closed) Deficiency (244/80-02-01):
Control rod alignment procedure CP 2.5. 1 was not followed in that for rod alignment performed December 20, 1979 the rod position for only one of eight Bank "A". rods was recorded; and for rod alignment performed August 9, 1979 rod positions: were.'recorded:
from computer readouts rather than from Control Room Bo'ard readouts.
In addition, data recorded for Calibration of Containment Spray Pumps Cooling Mater Outflow Transmitter FT-649 low flow alarm setpoint performed November 8, 1979 was not in tolerance nor was a required tolerance specified on the data sheet.
The inspector reviewed data for Control Rod Alignments performed September 11, December 2',
December 3,
and December 5,
1980 and determined that all data was properly recorded.
The inspector also observed that the calibration data sheet for Outflow Transmitter FT-649 has been revised to specify a tolerance of +2%.
(Closed)
Unresolved Item (244/80-02-02):
Procedure M-40,8, "Functional Testing of Hydraulic Snubber",
which requires a calibration of the velocity meter each day prior to use, does not require recording data for this calibration nor maintaining records of the calibration.
The inspector verified that procedure M-40.8 has been revised to include a data sheet for the calibration of the velocity meter.
In addition, the inspector reviewed the latest snubber functional test results and verified that the calibration was completed each day prior to use, that the data recorded was acceptable, and that the associated calibration data sheets were being maintained with the procedure.
(Closed)
Unresolved Item (244/80-02-03):
Data sheet for Procedure CP-402.0 needs to be revised to ensure that data for "T" average Repeater (Isolation Amplifier) TM-402W is recorded in volts as required by the procedure.'he inspector observed that the data sheet for CP-402.0 has been revised to record data for TM-402W 'in volts.
(Closed)
Unresolved Item (244/80-02-04):
Data sheet CP-4084.0 (Calibration of "C" Standby Auxiliary Feedwater Flow Indicators) did not reflect the expected output signals specified in procedure series CP-4084.
The inspector verified that data sheet CP-4084.0 has been revised to reflect the proper output signal (Cl'osed)
Unresolved Item (244/80-02-05):
The gauges used to measure fire-pump pressure and flow had not been calibrated nor had procedures been written to perform pump flow and pressure instruments were calibrated on May, 15, 1980; and reviewed the data observing no discrepancies.
The follow-ing procedures were issued on July 3, 1980 and will be used for future calibrations:
CP-3020, Motor Driven Fire Pump Discharge Pressure Gauge M-1, Revision 0;
CP-3021, Diesel Driven Fire Pump Discharge Pressure Gauge D-1, Revision 0; and, CP-3023, Fire System Flow Transmitter, FT 3023, Revision 0.
(Closed)
Inspector Follow Item (244/80-02-08):
Snubber tester pressure and tension gauges need to be calibrated on a regular basis and records of these calibrations maintained.
The inspector. verified that records of calibration of snubber tester pressur e and tension of gauges are being maintained by the Maintenance Shop; and that snubber testing procedure M40.8 requires that the gauges be calibrated within 12 months prior to their use.
Based upon action taken, this matter is closed.
/
(Open) Unresolved Item (244/80-02-06):
Halon system pressure gauges are not being calibrated.
The licensee performed an evaluation of this item and determined the gauges could not be calibrated without "dumping" the system, as the guages are non-isolable from the Halon tanks.
In addition, the tanks are weighed at the same time the pressure is checked.
The inspector again informed the licensee that the accuracy of gauges used to meet Tech-nical Specification surveillance requirements must be verified.
The inspector also observed, that although apparently connected to a
common header, the gauges on the eight Halon tanks ranged from 420 to 500 pSi.
Other methods of assuring the accuracy of these gauges such as a comparison of all gauges; comparison to a calibrated gauge placed in another part of the system; or modifications to install isolation valves were discussed.
The licensee stated a further engineering evaluation would be accomplished.
This item remains open pending completion of licensee action and subsequent NRC:RI review.
3.
Administrative Controls for Safet -Related Maintenance Administrative Controls were inspected to determine the licensee's program for compliance to the implementing requirements associated with the conduct of safety-related maintenance as specified in Technical Specification Section 6 and Regulatory Guide 1.33, guality Assurance Program Requirement The following procedures were reviewed.
A-403, Requisitioning Services from General Maintenance, Revision 1,
January 10, 1980.
A-501, Plant Procedures Preparation and Clarification, Revision 1,
May 21, 1979.
A-502, Plant Procedure Content and Format Requirements, Revision 12, September 23, 1980.
A503, Plant Procedure Adherence Requirements, Revision 1, October 27, 1980.
A-701, Receipt and Acceptance of Materials/Parts, Revision 3, February 5,
1980.
A-801, Control of Accepted Material, Parts and Components at Ginna Station, Revision 1, February 5,
1980.
A-804, Bulk Storage of Combustible Material and Their Use, Revision 0, May 23, 1980.
A-901, Control of Welding, Revision 1, September 22, 1980.
A-1001, Inspection and Surveillance Activities, Revision 6, August 22, 1980.
A-1010, Preventive Maintenance Program, Revision 0, April 1, 1980.
A-1011, Equipment Inspection Period and Lubricant List, Revision 1,
May 14, 1980.
A-1015, Three Month Lubrication and Maintenance Inspection, Revision 0, April 2, 1980.
A-1301, Maintenance and Inspection of Material Handling Equipment, Revision 2, February 8, 1980.
A-1401, Station Holding Rules, Revision 7, October 2, 1980.
A-1402, Bypass of Safety Function or Jumper Control, Revision 0, April 16, 1980.
A-1603, Maintenance Work Order and Trouble Report, Revision 1,
November 24, 198 A-53.3, Yalve Preventive Maintenance Program, Revision 1, June 9, 1980.
A-101, Ginna guality Assurance Program Implementation, Revision 0, June 6,
1979.
A-102.9, Maintenance Testing Program, Revision 0, February 22, 1979.
A-52.4, Control of Limiting Conditions for Operating Equipment, Revision 23, August 7, 1980.
A-1101, Performance of Tests, Revision 1, April 21, 1979.
guality Assurance Manual, Ginna Station.
No unacceptable conditions were identified.
4.
Review of Im lementation of Safet -Related Maintenance Activities a.
A sampling inspection was conducted of selected safety-related main-tenance performed by the licensee to determine that:
Technical Specification requirements were satisfied while equip-ment was out of service; Selected maintenance activities had been conducted in accordance with administrative procedures as detailed in Paragraph 3;
An approved procedure was used for those maintenance activities which could be considered beyond the skills normally possessed by qualified maintenance personnel; Inspections of maintenance activities as required by admini stra-tive procedures were performed; and, Records to substantiate quality of work and parts used were available (this includes documentation associated with procurement, inspections, and test results) for a sample of parts that were listed on trouble reports as detailed in paragraph 4.b.
The inspection included a review of maintenance requests as detailed in paragraph 4.b and associated maintenance procedures.
b.
Documentation of the following maintenance activities were reviewed:
Maintenance Wor k Order and Trouble Report (TR) 80-3l52, Repair of Leak on RHR Return Line, Completed November 29, 1980; and Associated Procedure EM274, Weld Repair on TI-627 Connection, Revision 0, November 26, 1980;
TR-80-3018, Reset Source Range Ch.
32 Bistable, completed November 12, 1980; and associated procedure CP3210, Calibration and/or Maintenance of Source Range N-32, Revision 1, March 1, 1978; TR-80-2939, Disassemble and Repair Sticking Charging Valve AOV-294, completed November 11, 1980; and associated procedure M37.3, Maintenance on Copper-Vulcan Diaphram Operational Control Valves for AOV294, Revision 3, June 28, 1978; TR-80-2871, Replaced 1C Safety Injection Pump Suction Flange, completed November 11, 1980; and associated Procedure M-22. 12. 1, Safety Injection Pump Mechanical Inspection, Revision 4, April 18, 1980; TR-80-2786, Replaced
"A" Instrument Air Compressor Discharge Valves Repaired, completed October 21, 1980; and associated procedure M-11.21, Jay Air Compressors Inspection and Maintenance, lA Instrument Air Compressors, Revision 1, June 1,
1977; TR-80-2619, Repair Relay Room Smoke Detectors, completed September 30, 1980; and associated procedure M-67.6, Smoke Detector Main-tenance, Revision 3; March 5, 1980; 5.
Review of TR-80-2347, Boric Acid Flow Transmitter Erroneous Indication, completed September 4,
1980; and associated procedure RSSP-5.0, Revision 6, April 15, 1980; TR-80-2038, Repack
"C" Charging Pump Plunger, completed July 18, 1980; and associated procedure M-11.4.6, Charging Pump Stuffing Box Maintenance for 1C Charging Pump; Revision 1, March 2, 1978; TR-80-2018, Repair B - Main Steam Isolation Valve Bonnet Gasket, completed July 23, 1980; and EM-152, Repair of Main Steam Isola-tion or Check Valve Using "Furmanite" Process for Valve No. 3516, Revision 6, June 20, 1980; and, TR-80-1447, Replaced Seal on "A" RHR Pump, completed May 21, 1980; and associated procedure M-11. 15, RHR Pumps Inspection/Main-tenance 1A RHR Pump, Revision 4, June 13, 1979.
No unacceptable conditions were identified.
Safet -Related Maintenance Pro ram An inspection was conducted to determine adequacy of the licensee's overall program for the performance of corrective maintenance, equipment control and release for performance of maintenance, and establishment of a preven-tive maintenance program and to determine that:
Administrative controls for these programs had been established; Responsibilities for performing various aspects of the program had been designated; Procedures for inspection and maintenance of records of maintenance activities had been established; Preventive maintenance schedules had been established; Control of special processes had been established; Methods for equipment control during maintenance had been established; and, Maintenance program conformed to the following Regulatory Guides and ANSI Standards as specified in the Quality Assurance Manual, Ginna Station:
(1)
Regulatory Guide 1. 116, Quality Assurance Requirements for Installa-tion, Inspection, and Testing of Mechanical Equipment and Systems, Revision 0,
May 1977; (2)
ANSI 45.2.8-1975, Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants; and, (3)
Regulatory Guide 1.33-1972,
"Quality Assurance Program Require-ments (Operation)."
No unacceptable conditions were identified.
6.
Review of Housekee in and Cleanliness Pro ram An inspection was conducted to determine the adequacy of the licensee's overall program for the maintenance of general plant housekeeping, main-tenance of cleanliness and protection of open safety related systems and components, and the cleaning of systems and components and to determine that:
Administrative controls for these programs have been established; Requirements and responsibilities for general plant housekeeping have been established; Requirements and responsibilities have been established for protection of previously cleaned systems and components and for protection of open safety related systems which require special cleanliness controls;
Methods have been established for cleaning of systems and components which have special cleanliness requirements; and Housekeeping and cleanliness program conformed to the following Regu-latory Guide and ANSI Standards as specified in the Quality Assurance Manual, Ginna Station:
(1)
Regulatory Guide 1.37, Revision 0, March 1973, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Com-ponents of Mater-Cooled Nuclear Power Plants";
(2)
"Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants";
(3)
Regulatory Guide 1.39, Revision 2, September 1977,
"Housekeeping Requirem'ents for Mater-Cooled Nucle'ar Power Plants";
and, (4)
"Housekeeping During the Construction Phase of Nuclear Power Plants".
~Findin s
The Qu'ality Assurance Manual Ginna Station specifies adherence to the requirements of Regulatory Guide 1.39 which, in turn, makes ANSI N45.2.3-1973,
"Housekeeping During the Construction Phase of Nuclear Power Plants" applicable to operating nuclear power plants.
Addition-ally, the Quality Assurance Manual requires that implementing instruc-tions be established implementing the above requirements.
ANSI N45.2.3, in part, requires the establishment of houskeeping zones, housekeeping practices procedures, training and qualification of personnel in housekeeping and cleanliness practices, control of tools in certain zones, periodic inspection specific job sites, and maintenance of records of housekeeping and cleanliness controls.
The inspector determined that there were no implementing procedures addressing the above ANSI N45.2.3 requirements.
The licensee stated that, although the requirements of'ANSI N45.2.3 were not addressed in plant administrative or quality assurance pro-cedures, and zones of cleanliness were not specifically establi'shed, extensive precautions were take~ to assure that open systems were protected during maintenance.
ihe licensee also stated that individual maintenance procedures had specific instructions for protection of open systems during maintenance.
However, the inspector reviewed numerous procedures and did not observe any specific instructions or precautions protective of open system The inspector observed that, where required, in specific maintenance procedures, there were instructions for cleaning of components or certifying their existing cleanliness as acceptable.
The inspector determined that the procedures for cleaning of components as expressed in individual maintenance procedures were adequate and that there. was, a procedure for inspections for determining the adequacy of general plant housekeeping.
The inspector informed the licensee that specific implementing procedures were required to ensure compliance to the requirements of ANSI N45.2.3.
Failure to establish implementing procedures to meet the requirements of ANSI N45.2.3 is contrary to
CFR 50, Appendix 8, Criterion V and the guality Assurance Manual Ginna Station, Section 1 and is an item of noncompl i ance (244/81-01-01)
.
7.
Administrati on Control s for Faci1 it Procedures The inspector reviewed the Administrative Controls established by the licensee for the control of Facility Procedures as a basis for a more detailed review of individual procedures and procedure changes.
The follow-ing procedures were reviewed.
A-52.6, Operations Standing Orders, Revision 4, September 10, 1980.
A-52.7, Operations Plan, Revision, October 24, 1980.
A-501, Plant Procedures Preparation and Classification, Revision 1,
May 21, 1989.
A-502, Plant Procedures Content and Format Requirement, Revision 13, December 19, 1980.
A-503, Plant Procedure Adherence Requirements, Revison 2,
December 29, 1980.
A-601, Plant Procedure Document Control, Revision 6, December 19, 1980.
A-602, Plant Procedure Distribution, Revision 7, December 5,
1980.
A-603, Control of Engineering and Design Documents by Central Records, Revision 4, December 19, 198 A-205, PORC Operating Procedure, Revision 2, December 19, 1980.
8.
, Technical Content of Facilit Procedures
'acility procedures were reviewed on a sampling basis using FSAR System Descriptions, Piping and Instrument Diagrams and Technical Specifications, where necessary to verify that procedures were sufficiently detailed to control the operation or evolution described within Technical Specification requirements.
The procedures reviewed with respect to this area are marked by asterisk (~) in the next paragraph (Paragraph 9,
Review of Facility Procedures).
No unacceptable conditions were identified.
9.
Review of Faci lit Procedures a
The inspector reviewed facility procedures on a sampling basis to verify the following.
That the procedures, plus any changes, had been reviewed and approved in accordance with the requirements of Technical Speci-fications and the licensee's administrative controls.
That the overall procedure format and content were in conformance with the requirements of Station Administrative Procedures.
That checklists were used and were compatible with the stepwise instructions in the procedure.
That appropriate Technical Specification limitations had been included/referenced in the procedures.
That temporary changes were made in conformance to Technical Specification requirements.
b.
The following procedures were reviewed.
Administrative Procedures In addition to those procedures identified in detail 7 above, the following procedures were reviewed.
A-52. 1, Shift Organization and Responsibilities, Revision 9, October 30, 1980.
A-52.4, Control of Limiting Conditions for Operating Equip-ment, Revision 24, December 23, 198 A-54.1, Licensed Personnel Authority, Revision 2, June 14, 1979.
General Plant 0 eratin Procedures 0-1. 1, Plant Heat Up From Cold Shutdown to Hot Shutdown, Revision 51, December 19, 1980.
0-5, Load Variation, Revision 6, May 23, 1979.
0-5. 1, Load Reductions, Revision 16, November 29, 1979.
0-5.2, Load Increases, Revision 19, June 13, 1978.
0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Revision 7, September 22, 1980.
0-9, Shift Relief Turnover Control Room, Revision 3, November 8, 1980.
S stem 0 eratin Procedures S-6, Nuclear Instrumentation System, Revision 2, October 23, 1978.
S-9A, Spent Fuel Pit Purification and/or Cooling System, Revision 9, April 23, 1980.
S-9B, Removing Spent Fuel Purification and/or Cooling System From Service, Revision 2, May 23, 1979.
S-15.2, Flux Mapping Emergency Calibration Procedure, Revision 13, December 24, 1980.
S-15.3, Incore Movable Detector Alignment, Revision 2, October 20, 1978.
S-16A, Safety Injection System Alignment, Revision 19, January 28, 1980.
S-23.2. 1, Containment Purge Prestart Up Procedure, Revision 0,
May 23, 1979.
S-23.2.2, Containment Purge Procedure, Revision 13, September 17, 1979.
T-2A, Prestart Alignment of Instrument Air, Revision 4, March 26, 198 T-27.1, 1A'mergency Diesel Generator Prestart Alignment, Revision 14, October 20, 1980.
T-35. I., Functional Alignment of Control Room Air Handling Unit, Revision 1, January 5,
1981.
T-41.D, Motor Driven Aux Feed Pump Isolation and Restoration to Service Revision 2, June 21, 1979.
Alarm Res onse Procedures A-15, RCP 1B Component Cooling Mater Return High Temperature or Low Flow, Revision 0, May 23, 1979.
A-25, Containment Ventilation Duct Isolation, Revision, May 23, 1979.
A-14, N2 Accumulator Y801A Low Pressure, Revision 0, November 17, 1980.
A-25, Condensate System Lo Pressure, Revision 1,
December 27, 1979.
B-23, Boric, Acid Tank LoLo Level, Revision 0, May 23, 1979.
D-26, Source Range Hi Flux Level Rx Trip, Revision 0, May 23, 1979.
E-9, Intermediate Range Loss of Compensating Voltage, Revision 0,
May 23, 1979.
H-8, Instrument Air Low Pressure, Revision 0, May J-24, Emergency Diesel Generator 1-A Panel, Revision 0, May 23, 1979.
Emer enc Procedures E-S, Control Room Inaccessibility, Revision 11, December 28, 1978, E-14, High Radiation Coolant Activity, Revision 7, October 31, 1979.
E-20, Immediate Boration, Revision 9, December 28, 1979.
E-29.1, Loss of Normal Feedwater (Not Recoverable),
Revision 5, January 17, 198 E-29.2, Loss of Normal Feedwater (Recoverable),
Revision 1,
July 17, 1979.
E-32, Loss of Instrument Air, Revision 4, December 28, 1979.
Maintenance Procedures M-11-8F, RCP Internal Inspection, Revision 3, February 6, 1980.
M-11. 12. 1, Safety Injection Pump, Mechanical Inspection, Revision 5, November 21, 1980.
M-37. 1, Maintenance of Pressurizer Spray Valves 431A and 431B, Revision 3, September 17, 1979.
M-37. 14, Inspection and Maintenance of "B" Loop Accumulator's Dischargable'heck Valve, Revision 4, June 6, 1979.
M-38.2, 1A Inverter/CVT Maintenance or Repair, Revision 3, June 20, 1980.
M-47. 1, Inspection of Pressurizer Internals, Revision 8, December 5,
1980.
- M-57. 1, Power Range NIS Detector Replacement, Revision 3, November 15, 1980.
EM 204, Seal Weld MOV-700 RHR From Loop "A", Revision 0, May 3, 1978.
EM-217, Installation of a New Sample Delay Coil, Revision 1,
February 10, 1979.
EM-260, Repair of Fuel Assembly, Revision 0, February 15, 1980.
No unacceptable conditions were identified.
10.
Procedure Chan es Resultin From Technical S ecification Amendment The inspector reviewed License Amendments 20 through 34, and verified that applicable procedures were revised as necessary to reflect the changes to the Technical Specifications.
No unacceptable conditions were identifie.
Review 'of Standin Orders The inspector reviewed Operation's Standing Orders, revised/reviewed January 9,
1981, for possible conflict with facility procedures or Tech-nical Specification requirements.
No unacceptable conditions were identified.
12.
Checklists and Related Forms Operations Department procedures, including routine surveillance tests, checklists and related forms in working files, were 'reviewed to see that current revisions and on-the-spot changes were posted.
No unacceptable conditions were identified.
13.
Chan es to Procedures as Detailed in the Safet Anal sis Re ort Pursuant to
CFR 50.59 a
and b
The inspector verified, on a sampling basis, that changes made to facility
~ procedures during the past fifteen month period were in compliance with 10 CFR 50.59(a)
requirements and that records of these changes were maintained in compliance with 10 CFR 50.59(b).
For the procedures reviewed, the licensee'had determined that
CFR 50.59 safety evaluation documentation was not required (no change in procedures as described in the FSAR).
The inspector found no discrepancies in the licensee evaluation and had no further questions in this area.
14.
Control Room Observations and Faci lit Tour The inspectors toured accessible areas of the Turbine/Generation Building, Auxiliary Building, Diesel Generator Screen House and Control Room.
During the tour the inspectors discussed plant operations and observed housekeeping, radiation control measures, monitoring instrumentation and controls for Technical Specification compliance.
In addition, the inspectors observed control room operations for manning and operation in accordance with admin-istrative and Technical Specification requirements.
No unacceptable conditions were identified.
15.
Mana ement Meetin s
Licensee management was informed of the purpose and scope of the inspection at the entrance interview, and the findings of the inspection were period-ically discussed with the licensee represe'ntatives as follows:
Date Re ortable Details Covered January
January
January
Entrance Interview 6.b Exit Interview The inspector conducted an exit interview with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection, where the findings of the inspection were presented and acknowledge./