IR 05000244/1978026
| ML17244A323 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/12/1978 |
| From: | Baunack W, Kister H, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17244A322 | List: |
| References | |
| 50-244-78-26, NUDOCS 7901190248 | |
| Download: ML17244A323 (22) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I R
p N
. ~50.244 78-26 Docket No.
50-244 License No.
DPR-18 Priority Category C
L'icensee:
Rochester Gas and Electric Cor oration 89 East Avenue Rochester, New York 14649 Facility Name:
R.
E. Ginna Inspection at:
Ontario, New York Oi Inspection conducted:
Inspectors:
W.
H. Baunac
>mme November 28 - December 1,
1978
,
Reac Inspector an, Re tor Inspector l~7 date signed date signed
.J J~
7Z Approved by:
um erg, eac nspector
.
B. Kist r, Chief, Nuclear Support Section No. 2, RO&NS Branch
, 'ate'signed j2 ate signed Ins ection Summar Ins ection on November 28 - December 1,
1978 Re ort No. 50-244/78-26 reas Ins ecte
Routine, unannounce snspectson by regsona based inspectors of icensee action on previous inspection findings; administrative control of safety-related maintenance; review of'afety-related maintenance activities; technical qualifications; administrative controls for facility procedures; technical content of facility procedures; review of facility procedures; pro-cedure changes resulting from technical specification amendments; review of standing orders; control room operations; and facility tour s.
This inspection involved 55 inspector-hours on site by three NRC regional based inspectors.
Results:
No items of noncompliance were identified during the conduct of this
'Illspectlon.
Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- W. Backus, Operations Supervisor S. Bullock, guality Control Engineer L. Depew, Shift Foreman C. Edgar, Instrument and Control Foreman D. Hamelink, Maintenance Supervisor R. Junot, Shift Foreman C. Peck, Operations Supervisor
- B. Snow, Plant Superintendent
- S. Spector, Maintenance Engineer The inspectors also interviewed other licensee employees, including members of the technical and engineering staff, reactor operators,"
and general office personnel.
- denotes those present at the exit interview.
Z.
Licensee Action on Previous Ins ection Findin s
(Closed)
Unresolved Item (244/78-11-02):.
The inspector reviewed Maintenance Procedure M-15.1,
"A or B Diesel Generator Removal from Service,"
Revision 7, July 25, 1978, and verified that the procedure had been revised to incorporate the multi-point cali-bration check of the oil storage tank level instruments during each refueling.
3.
Administrative Control of Safet -Related Maintenance The inspector reviewed the licensee's program for administrative control of safety-related maintenance activities, as described in the following administrative procedures:
A-18, Multileaf Trouble Report and Work Order, Revision 7, September 13, 1977.
A-30.3, Plant Procedure Content and Format Requirements, Revision 19, November 13, 197 A-30.4, Plant Procedure Adherence Requirements, Revision 2, December 15, 1977.
A-36, Station Holding Rules, Revision 11, May 25, 1978.
A-47, Record and Document Reten'tion, Revision 7, July 14, 1976.
A-50.8, Maintenance Training Program, Revision 4, October 10, 1977.
A-52.4, Control of Limiting Conditions for Operating Equip-ment,- Revision 12, April 5, 1978.
This review was conducted as a fimiliarization with the licensee's procedural requirements in this area and as an audit with respect to Technical Specification, Section 6, Administrative Controls, Regulatory Guide 1.33, Quality Assurance Program Requirements, and ANSI N18.7, Administrative Controls for Nuclear Power Plants.
Based on this review, no items of noncompliance were identified.
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4.
Review of Safet -Related Maintenance Activities a.
The inspector reviewed safety-related maintenance conducted by the licensee on a sampling basis to verify that:
Limiting Conditions for Operation (LCOs) were met while equipment was out of service; Required administrative approvals were obtained to per-form the work; An approved procedure was used where required; Required inspections were performed; QA/QC records were available to substantiate quality of work and parts used; The maintenance was performed by qualified maintenance personnel; and,
A Reportable Occurrence Report, if required, by Technical Specifications, was submitted based on review of circum-stances associated with the maintenance activity.
The documentation associated with the following safety-related maintenance activities was reviewed:
lA Charging Pump Vari Drive Overhaul, January 18, 1978, performed in accordance with procedure M-11.4.4.
Work Order 78-49, B Charging Pump, January 7, 1978, performed in accordance with procedure M-11.4.4.
IC Salt Water Pump Breaker, March 14, 1978, performed in accordance with procedures M-32 and M-32.1.
B Diesel Generator Inspection, March 27, 1978, per-formed in accordance with procedure M-15.1.
A Service Water Pump - Changed Expansion Joint, May 2, 1978, performed in accordance with procedure M-11.10.
B Containment Recirculation Fan-Replace Outboard Fan Bearing, May 10, 1978, performed in accordance with pr ocedure M-11. 34.1.
MS-146-B (Shock Suppressor)
- Remove and Replace, July 7, 1978, performed in accordance with procedure M-40.1.
860B Valve will not Stroke Closed, June 29, 1978, per-formed in accordance with procedure M-64.1.
1D CY Recirculation Fan-Splices, September 27, 1978, performed in accordance with procedure EM-208.
Work Order 78-1916, B Diesel Generator - Breaker DC Control Malfunction, August 16, 1978, performed in accordance with procedure M-32.1.
Work Order 78-2052, V625 HCV, August 31, 1978, per-formed in accordance with procedure CP-62 Shock Suppressor FW-30 - Oil Leak Indicated, October ll, 1978, performed in accordance with procedure M-40.1.
Work Order 78-86, B Charging Pump, January ll, 1978, performed in accordance with EM-197.
Work Order 78-634, Control Rod Indication, March 21, 1978, reviewed calibration data for calibration per-formed following maintenance.
Work Order 78-669, IRPI's March 24, 1978, reviewed calibration data for calibration performed following maintenance.
C.
During the review of maintenance activities conducted using the maintenance work order and trouble report form, the inspector noted that section 1.2 of several work orders had not been completely filled out, this appeared to be due to a lack of detailed guidance in procedure A-18 which describes the use of the form.
The licensee stated this procedure would be reviewed and revised as necessary to clarify the preparation of work orders.
This item will be reviewed during a future inspection.
(244/78-26-01)
5.
Techni cian ua1 ificati ons The inspector reviewed the qualification records of selected individuals having responsibility for maintenance of safety-re-lated systems and components to verify that their experience level and training were in accordance with the guidelines set forth in ANSI N18.1, Selection and Training of Nuclear Power Plant Personnel.
No unacceptable items were identified.
6.
Administrative Controls for Facilit 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 following procedures were reviewed:
A-19, Changes in Written Procedures, Revision 28, April 5, 1978.
A-30.2, Plant Procedure Classification, Review, Approval and Distribution Requirements, Revision 18, November 13, 1978.
A-30.3, Plant Procedure Content and Format Requirements, Revision 19, November 13, 1978.
A-30.4, Plant Procedure Adherence Requirements, Revision 2, December 15, 1977.
A-37, Conduct of Operations for Safety Evaluations as related to Facility Modifications, Special Tests, or Experiments, Revision 7, August 18, 1978.
A-37.1, System Modification Requirements, Revision 2, July 21, 1978.
A-52.6, Operations Standing Order, Revision 3, November ll, 1977.
A-52.7, Operations Plan, Revision 1, March 25, 1977.
QC-502, Plant Procedures, Revision 6, August 17, 1976.
QC-602, Plant Procedure Document Control, Revision 12, August 23, 1976.
QC-1701, Quality Assurance Records, Revision 11, July 28, 1978.
QC-1703, Record Storage Facility and Equipment, Revision 3, August 17, 1976.
No items of noncompliance were identifie N
7.
Technical Content of Facilit Procedures Facility 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 de-scribed within Technical Specification Requirements.
The proce-dures reviewed with respect to this area are marked by asterisk (*)
in the next paragraph (Paragraph 8, Review of Facility Procedures).
No items of noncompliance were identified.
8.
Review of Facilit 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 Specifications and the licensee's administra-tive controls.
i That the overall procedure format and content were in conformance with the requirements of ANSI N18.7-1972,
"Administative Controls for Nuclear Power Plants."
That checklists, were used, were compatible with the stepwise instructions in the procedure.
That appropriate Technical Specification limitations had been included/referenced in the procedures.'hat temporary changes were made in conformance to Tech-nical Specification requirements.
b.
The following procedures were reviewed:
Administrative Procedures In addition to those procedures identified in detail
above, the following procedures were reviewed:
A-3, Containment Access, Revision 12, November 15, 1978.
A-20, Control Room Logs, Revision 8, November 13, 1978.
A-36, Station Holding Rules, Revision ll, May 25, 1978.
A-52.2, Control Locked Valve Operation, Revision 22, July 28, 1978.
General Plant 0 eratin Procedures
- 0-1.1D, Pre-Heatup Plant Requirement Checklist, Revision 6, July 22, 1977.
0-2.2, Plant Shutdown from Hot Shutdown to Cold Condition, Revision 33, May 25, 1978.
- 0-3.1, Boron Concentration for the Xenon Free All Rods In-Most Reactive Rod Stuck Out Shutdown Margin, Revision 5,
May 9, 1978.
S stem 0 eratin Procedures'-6.1, quadrant Power Tilt Monitor Operability Check, Revision 1, July 8, 1977.
S-7A, Refueling Water Storage Tank Purification, Revision
, 4, April 14, 1977.
- S-13A, RHR System Lineup for Safety Injection, Revision 10, April 25, 1978.
- S-23 F 1, lA Containment Recirculation Fan Cooler Pre-Startup, Revision 0, December 27, 1977.
T-27.1, 1A Emergency Diesel Generator Pre-Start Align-ment, Revision 8, December 15, 1977.
T-36.1, Station Service Water-Header Valve Alignment for Two Loop Operation, Revision 2,'uly 6, 1978.
Alarm Res onse Procedures A-9, RHR Pump Cooling Water Outlet Low Flow, Revision 0, March 4, 197 AA-5, Component Cooling Surge Tank High Level, Revision 0, March 4, 1977.
C-25, Containment Vent Duct Isolation, Revision 0, March 4, 1977.
D-21, Steam Line Lo Lo Pressure-Loop A, Revision 0, March 7,
1977.
D-26, Source Range Hi Flux Level Reactor Trip, Revision 0, March 7, 1977.
J-24, Emergency Diesel Generator 1-A Panel, Revision 0, March 10, 1977.
Emer enc Procedures E-4, Station Blackout Operation, Revision 11, May 26, 1977.
- E-8, Loss of Reactor Coolant Flow, Revision 7, March 25, 1978.
E-17, Loss of Residual Heat Removal, Revision 5, March 3,
1977.
- E-38, Loss of Service Water, Revision 1, June 8, 1977.
Maintenance Procedures
- M-11.10, Major Inspection of Service Water Pump, Revision 7, June 26, 1978.
- M-ll;15, RHR Pumps Inspection/Maintenance, Revision 3, June '26, 1978.
M-15.1, 'A'r 'B'iesel Generator Removal from Service, Revision 7, July 25, 1978.
M-37.20, Inspection and Repair of Main Steam Isolation Valves, Revision 6, August 7, 197 M-57.1, Power Range NIS Detector Replacement, Revision 1, June 28, 1978.
N-81, Safeguard Rack Ventilation and Containment Isola-tion Relays Replacement, Revision 0, April 25, 1978.
No items of noncompliance were identified.
9.
Procedure Chan es Resultin from Technical S ecification Amendment The inspector reviewed License Amendments 15 through 19, and verified that applicable procedures were revised as necessary to reflect the changes to the Technical Specifications.
No items of noncompliance were identified.
10.
'Review of Standin Orders
.
The inspector reviewed Operation's Standing Orders, revised/reviewed August 3, 1978, for possible conflict with facility procedures or Technical Specification requirements.
No items of noncompliance were identified.
Control Room 0 erations 12.
The inspectors observed control room operations on both day and
. evening shifts for proper control room manning, and facility operation in accordance with selected Administrative and Technical Specification requirements.
Control room log sheets, and lighted annunciators were reviewed and discussed with operators.
No-items of noncompliance were identified.
~Flic T
On several occasions during the inspection, tours of the facility were conducted of the Turbine Building, Demineralizer Building, Auxiliary Building, Diesel Generator Rooms, Screen House, and portions of the security fence.
During the tours, the inspector discussed plant operations and observed housekeeping, monitoring instrumentation, temporary procedure change adherence, and controls for Technical Specification compliance.
No items of noncompliance were identifie.
Exit Interview The inspectors met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on December 1,
1978.
The inspector summarized the scope and findings of the inspection.