IR 05000244/1978027
| ML17244A351 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/22/1978 |
| From: | Beckman D, Keimig R, Raymond W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17244A350 | List: |
| References | |
| 50-244-78-27, NUDOCS 7902010184 | |
| Download: ML17244A351 (18) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
4
. ~5G-244 75-27 Docket No.
50-244 Region I License No.
DPR-18 Priority Category Licensee:
Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 Facility Name:
R.
E. Ginna Nuclear Power. Plant, Unit
Inspection at:
Ontario, New York Inspection cond c
Inspectors:
0 cember 6-8, 1978 an, eac or nspec or date signed (2-2L.7E aymon
,
eac or nspec or date signed Approved by:
.
R.
K g,
ie eac or rogects Section
. 1, R
S Branch date signed ZZ-8 date signed Ins ection Summar
Ins ection on December 6-8, 1978 Re ort No. 50-244 78-27 Areas Ins ected:
Routine, unannounced inspection started on a backshift, by regiona based inspectors of plant operations including: facility logs, records and plant status; status of previous outstanding items; qualification of stem mounted limit-switches used for post-accident valve indication; and observation of post-trip plant recovery activities.
The inspection involved 30 inspector-hours onsite by two NRC regional based inspectors.
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev.
Apr il 77)
e
DETAILS Persons Contacted Mr.
Mr.
Mr.
- Mr.
Mr.
, Mr.
Mr.
Mr.
Mr.
Mr.
Mr.
- Mr.
W. Backus, Operations Supervisor L. Brodie, Head Control Operator S. Bullock, guality Control Engineer C. Edgar, Instrument and Control Foreman D. Horning, Shift Foreman R. Latz, Maintenance Foreman R. Morrill, Training Coordinator G. Paris, Instrument and Control Supervisor C. Peck, Operations Engineer T. Rakiewicz, Instrument and Control Technician M. Shaw, gua1ity Control Inspector B. Snow, Plant Superintendent The inspectors also interviewed other licensee personnel, including members of the operations, maintenance, health physics and general office staff.
h
- denotes those present at exit interview.
Licensee Action on Previous Ins ection Findin s (Closed)
Unresol ved item (75-20-01): Differentiation between main-tenance and modification activities with respect to administrative controls to be applied.
The inspector reviewed the guality Assurance Manual (JAM) Glossary of Terms, revised December 1, 1978; the JAM, Section 3, Configuration Control, Revision 7; and Procedure A-37.1, System Modification Requirements, Revision 2.
These documents collectively provide the definitions and descriptions required to distinguish modifications from maintenance activities and provide controls for the management of changes to the plant configuration.
The documents also provide guidance and requirements for the appli-cation of appropriate codes and standards to each qctivity.
(Open)
Unresolved item (75-21-07): Procedural guidance for backup plant cooldown without preferred and alternate systems available.
The licensee has undertaken development of methods for plant cool-down when areas critical for safe shutdown are unavailable due to fire.
These methods, described in narrative form, have been issued in a report which is used during operator training and requalification training.
The licensee presently does not plan to issue detailed
procedures describing the various shutdown methods.
Although adequate operator training has been given in this area this item will remain unresolved pending review of the above report and evaluation by NRC:RI of the need-for detailed procedures.
(Closed)
Unresolved item (77-09-01): Describe methods for disseminating pertinent LER type information to nonlicensed personnel.
The inspector reviewed procedures A-50.8, Maintenance Training Program, Revision 4, and A-50.10, Operator Incident Review, Revision 4, and determined that they provide for dissemination and review of pertinent LER's issued by this and other facilities to the appropriate nonlicensed and licensed personnel.
The inspector verified that the provisions of A-50.8, are being implemented through discussions with maintenance personnel and review of routing copies of the information.
(Open)
Unresolved item (77-14-07):
Resolve conflict in Operator Requal-ification Program record keeping requirements between gC-1701 and A-50.6.
The conflict in retention time requirements in the above procedures is being reviewed by the licensee to ensure that all applicable gA Program and
CFR 55 record requirements are properly addressed by the procedure revisions.
The licensee stated that, in the interim, records are being retained to meet the most conservative requirements.
This item will remain unresolved pending revision of the subject procedures and review by NRC:RI.
(Closed)
Unresolved item (78-01-01):
Common ventilation system for Battery Rooms A and B with intake and exhaust to Turbine Building.
The licensee has completed modification SM76-21 which provides for separa-tion of ventilation exhaust flows with individual discharge to the Turbine 'Building.
The inspector reviewed the documentation associated with the modification and had no further questions on this matter.
(Closed)
Unresolved item (77-21-02):
Followup on LER's 77-09, 77-18 and 77-20.
The inspector noted that the licensee's investigation of cause and -corrective actions regarding charging pump discharge piping leaks have been reviewed previously by NRC:RI and found acceptable, as documented in NRC:Region I Inspection Reports 50-334/77-21 and 50-334/78-01.
The inspector had no further questions concerning this matter and this item is considered resolved.
(Open)
Unresolved item ( 76-.16-06):
A31" Yolatile Treatment (AVT)
System Review.
This item was unresolved in NRC:RI Inspection Report 50-244/78-08 pending subsequent PORC and NSARB review of the detailed safety analysis for SM75-41, "Full Flow Condensate Demineralizer and Blowdown Heat Recovery System."
The inspector reviewed the SM75-41
design package, including the Design Criteria Document, Revision 1,
.and accompanying safety analysis.
Additionally, PORC meeting minutes for 1977 and 1978 were reviewed to ascertain whether the item had been addressed.
The inspector was unable to determine whether or
- not the item was addressed subsequent to PORC meeting 53-76, during, which preliminary discussions were held, and the licensee stated that the matter would be reviewed to resolve the status of the PORC and NSARB activity in this area.
The inspector noted that the licensee concluded during PORC meeting 53-76 that operation of the AVT system does not constitute an unreviewed safety question, that no reduction in margins to safety limits for accidents previously analyzed is involved and that no changes to the Technical Specifications are required.
In a telephone conversation with licensee representatives on December 14, 1978,. the licensee stated that this item had not been addressed by the Safety committees subsequent to PORC meeting 53-76 (1976)
and that further actions would be taken to resolve the matter.
This item will remain unresolved pending completion of the licensee's actions in this area and subsequent review by NRC:RI.
3.
Review of Plant 0 erations a 0 Shift Lo s and 0 eratin Records (1)
The inspector reviewed the following logs and records:
Official Record, December 1-8 Shift Foreman Record, December 1-8 Auxiliary Operators'rimary Side Logs, December 1-8 By-pass of Safety Function and Jumper Control Request (78-32 through 78-35)
Completed Ginna Station Event Reports (A-25.1) for events which occurred during the period September 6 through October 5, 1978 Daily Surveillance Log, October 27 - October
and December 1-6, 1978 Operation Plans, November,25 - December 8, 1978 RCS Leakage - Surveillance Logs (5-12.2)
Daily Chemistry Logs, November - December 1978 Completed records issued for control of LCO's for Operating Equipment (A-52.4) during the period October 11-30, 1978 (2)
The following Periodic Test procedures, completed during December 1-6, 1978 were reviewed:
PT-2.2, RHR System, Revision
PT-2.1, SI Pumps, Revision
PT-6.3.1 thru 6.3.4, Power Range NI Channels 41-44, various revisions PT-2.5.2, AOV quarterly Test, Revision
PT-12.1,. Emergency Diesel Generator lA, Revision
The. inspectors also reviewed the Monthly Surveillance Schedule for December.
(3)
The logs and records were reviewed to verify that:
Log sheet entries are filled out and initialed Log entries involving abnormal conditions are sufficiently detailed Log book reviews are being conducted by the staff Operating orders do not conflict with the intent of the Technical Specification (TS)
Jumper log entries do not conflict with TS Problem identification reports confirm compliance with TS reporting and LCO requirements (4)
Conformance with Technical Specification requirements was directly observed by the inspectors during the period. 2000-2200 hours on December 6, 1978.
The inspectors observed various control board switch alignments, instrument indications and records to confirm that the following selected TS require-ments were me TS 3.1.5, RCS Leakage Determinations TS 3.1.6, RCS Chemistry TS 3.2.2, Charging Pump Operability and Boric Acid Tank level, temperature and chemistry TS 3.1.1, Refueling Water Storage Tank level and chemistry; SI Accumulator level, pressure and chemistry; SI Pump, RHR Pump, and RHR Heat Exchanger operability and system valve alignments TS 3.3.2, Spray Additive Tank level and chemistry, Containment Spray Pump operability and Fan-Cooler Unit operability TS 3.3.3, Component Cooling Pump operability TS'.3.4, Salt Mater System Pump operability TS 3.10.1, Control Rod Insertion Limits TS 3. 10, Indicated Axial Flux Difference Additionally, the control board was observed for annunciators that should not normally be lighted during the existing plant conditions.
The reason for each alarmed annunciator was adequately explained.-by the Control Operator.
(5)
Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifi-cations and the following procedures:
A-17, "Plant Operations Review Committee Operating Procedure, Revision
A-20, "Control Room Logs," Revision
A-25, "Reporting of Unusual Plant Conditions," Revision
A-25.1, "Ginna Station Event Report," Revision
A-46, "Bypass of Safety Function and Jumper Control,"
Revision
A-52.2, "Control of Locked Valve Operation,"
Revision
A-52.1, "Shift Organization, Relief and Turnover,"
Revision
A-52.4, "Control of Limiting Conditions for Operations,"
Revision
A-52.5, "Control of Limiting Conditions for System Specifications,"
Revision
A-52.6, "Operations Standing Order," Revision
A-52.7, "Operations Plan," Revision
gC 1701 "guality Assurance Records,"
Revision
No items of noncompliance were identified.
4.
Plant Tri and Recover Activities
~
~
~
a.
Durin this ins ection D
g p
on ecember 7, 1978, the unit reduced power to less than 505 to effect repairs on leaking tubes in No.
3A LP Feedwater Heater.
At approximately 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, a
High/Low Oil Level alarm was received on the B Reactor Coolant Pump.
The on duty operator secured the affected pump and manually tripped the turbine generator from 495 power.
The reactor remained critical until Steam Generator level reached its Low-Low setpoint due to the power and flow transients at which time the -reactor tripped.
The plant was placed and maintained in a hot shutdown condition during the subsequent repairs to the Feedwater Heater and Reactor Coolant Pump inspection.
The actions taken by the operators in response to the initiating alarm were found to be consistent with the requir'ements of Alarm Response Procedure A-32, Plus-Minus RCPlB Oil Level, Revision 0.
b.
The inspector reviewed the initiating circumstances and reviewed and observed portions of the recovery activities.
All automatic protection equipment appeared to function as require Inspector observation of recovery activities immediately following the trip identified no discrepancies.
Subsequent review of the evolutions performed to place and maintain the unit in hot shutdown indicated that the unit had been operated in accordance with applicable Technical Specification and procedural requirements.
At the close 'of this inspection, preparations were being made to perform a reactor startup.
The RCPlB low oil level alarm had been confirmed as valid and oil had been added to re-establish a normal level.
The licensee stated that the pump oil level had remained sufficient to preclude pump damage and the low level alarm appeared to be due to normal oil consumption.
The No.
3 Feedwater Heater had been repaired and was being returned to service.
No items of noncompliance were identified.
5.
Use of Stem Mounted Limit Switches SMLSs In Safet Related S stems The use of SMLSs sn safety related plant systems at Gonna has been reviewed previously by NRC:RI.
Licensee reviews of plant systems in response to IE Bulletin 78-04 concluded that no SMLSs are used to provide a "latch-in" function as part of the valve control circuitry in plant safety related systems'that would be subjected to adverse environmental conditions.
Licensee actions in this area were reviewed by NRC:RI and found acceptable, as documented in Inspection Reports 50-244/78-17 and 50-244/78-18.
During this inspection, the licensee was requested to address whether SMLSs of the type referenced in IEB 78-04 were used to provide control room position indication of power operated valves.
The inspector presented the NRC position that power operated containment isolation valve position indication to the control room operator is essential during and following a LOCA.
As such, the licensee should ensure that SHLSs used on power operated valves inside of containment are qualified for the accident environment or provide technical justification for any exception to the NRC position.
During subsequent onsite reviews and in a telephone conversation with licensee representatives on December 14, 1978, the inspector noted that the following power operated valves located inside containment use NAMCO Model D2400X SMLSs (Referenced in IEB 78-04) to provide position indi-cation in the control room:
Valve No.
Desi nation 371 951 953 955 CDV1A CDV1B PEV/I PSV/I The inspector acknowledged the licensee's coranitments and stated that NRC:RI will review the evalution at a later date.
This item is unre-solved pending completion of. the licensee's and NRC:RI review.
(50-244/78-27-01}
6.
Unresolved Items letdown isolation valve pressurizer steam space sample line pressurizer liquid sample line loop B hot leg sample line containment depressurization containment depressurization purge exhaust valve purge supply valve This valve list'was developed from observation of plant systems and from procedures RSSP 2.1, Safety Injection Functional Test, Revision 8, May 26, 1977, and E-l.l, SIS Actuation, Revision 6, August 31, 1978.
The licensee stated that further engineering review would be required to determine the proper corrective actions to be taken.
The licensee stated that this review would be completed and the results reported to NRC:RI by telephone by December 22, 1978.
Unresolved items are those items for which further information is required to determine whether the items are acceptable items, items of noncompliance, or deviations.
Unresolved items are discussed in Paragraph 5.
7.
Exit Interview A management meeting was held with licensee personnel (denoted in Paragraph 1) at the conclusion of the inspection.
The purpose, scope and findings of the inspection were discussed as they appear in the details of this report.
The licensee acknowledged the transfer of lead responsibility for the NRC:RI inspection and enforcement activities at the R.
E. Ginna station from Mr.
W.
Raymond to Mr.
D. Beckman.
Subsequent to the inspection, on December 13 and 14, 1978, telephone conversations were held between Mr. D.
Beckman and Messrs.
Snow and Noon to further discuss the items in paragraphs 2 and 5 of this repor li