IR 05000244/1979012
| ML17249A233 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/14/1979 |
| From: | Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17249A232 | List: |
| References | |
| 50-244-79-12, NUDOCS 7911020467 | |
| Download: ML17249A233 (28) | |
Text
U.S..NUCLEAR REGULATORY COtlMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Repor t No.
50-244/79-12 Docket Ho.
50-244 License No.
DPR-18.:
Priority Category R..
Ma ows i, Reactor Inspector
,
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 conducted:
July 31-August 3, 1979 Enspector s:,
~ G.)wi'Mc'zwsMc gc date signed D.
eckman, Reactor Inspector d te signed dat signed Approved by:
R.
R. Keimig, ief, Reactor Projects Section No. 1, ROSNS Branch d te si ned Ins ection Summar:
Ins ection Jul 31 - Au ust 3, 1979 Re ort No. 50-244/79-12
Areas 'Ins ected:
Routine, unannounced inspection of:
previously identified unresolved
) ems; p an operations review; observation of activities associated with startup from cold shutdown conditions; plant tours; and, actions taken in response to IE Bulletins No. 79-02, Revision 1, and 79-13.. The inspection involved 44 inspector-hours onsite by two NRC regional based inspectors.,
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
79< g Ogp
DETAILS 1.
Persons'Contacted
- Mr. W.
- Mr. J.
- Mr.. A.
- Mr. E..
- Mr. C.
- Mr.
D.
- Mr. G.
- Mr. T.
Mr., R..
- Mr. J.
Mr. B.
Mr. B.
- Mr.. S.
- Mr. J.
Backus, Operations Supervisor Bodine, Station QC Curtis, NDE Coordinator Demerit,. HP and Chemistry Supervisor Edgar, IKC Foreman Gent,, Results and Test Supervisor Larriza, Technical Engineer
'eyer, Nuclear Engineer Morill, Training Coordinator Noon, Assistant Superintendent Quinn,, Health Physicist Snow, Superintendent Spector, Maintenance Engineer St. Martin, Project Liaison Engineer The inspectors also interviewed other licensee personnel including members of the operations, maintenance, engineering and general office staffs.
- denotes those present at the exit interview.
Licensee Action on Previous Ins ection Findin s (Closed)
Unresolved Item (79-08-03):
'Licensee to incorporate switch and breaker lineups into alignment procedures for Auxiliary Feedwater and Component Cooling Water Systems.
The inspector reviewed procedures T-41A, Alignment of Auxiliary Feedwater System Prior to Power Operation, Revision 15 and S-BA, Component Cool,ing Water System Star tup and Normal Operation Valve Alignment, Revision 9, and found them.to include switch and breaker alignment steps for appropriate equipment in each system.
The individual procedure steps added to the procedures were verified, on a sampling basis, to be accurately written with respect to system flow and electrical diagrams.
This item is resolved.
(Closed), Unresolved Item (79-08-04):
Station to issue Preventive Action Report(s)
(PAR's) for procedure and drawing errata.
The inspector reviewed PAR 34A-79 and PAR 34B-79, both issued on June 5,
1979.
The PAR's included the errata identified during Inspection 79-08 and were targeted for completion of corrective action by July 18 and October 12, 1979 respectively.
PAR 34A-79 addressed the errata associated with operation, surveillance, and mechanical maintenance procedures.
The inspector reviewed the response to PAR 34A-79 and confirmed the accuracy and adequacy of the response on a sampling basis by reviewing the procedures affected by each line item and verifying that the action specified by the PAR had been accomplished.
The inspector noted that seven of the forty-seven
,line items of the PAR are under continuing review and that the PAR remains open pending completion of the work and closeout by Quality Contro PAR 34B-79 addresses errata associated with ISC Department calibration and surveillance procedures and resolution of its line items is still in'rogress.
Discussions with the IKC Foreman responsible for PAR resolution indicated that progress is being made toward completion of
'he procedure corrections prior to the October 12 commitment date.
The licensee has contracted a consultant to conduct a comprehensive review and upgrading of I&C Department procedures commencing on August 6, 1979.
The findings of the subject PAR will be incorporated into that effort.
Based on the progress. observed by the inspector and the continuing attention provided to this matter by the responsible departments and station guality Control, this item is resolved.
3.
Plant 0 erations Review a ~
Shift.Lo s and 0 eratin Records (1)
The inspector reviewed the following logs and records:
Official Record, July 1-31, 1979 Shift Foreman Record, July 1-31, 1979 Shutdown Log Sheets
- Control Room, July 6-31, 1979 Temporary Wire Control Logs (Through 79-5)
By-pass of Safety Function and Jumper Control Request, (Through 79-19)
Completed Ginna Station Event Reports (A-25.1) for events which occurred during the period October 13, 1978 - January 26, 1979 Daily Surveillance Log, July 1-31, 1979 Monthly Surveillance Log, July - August, 1979 Operator Plans, July 1 - August 1, 1979 Station Holding Log RCS Leakage - Surveillance Logs Event Reports (A-25.1) issued for the period June 1-July 31, 1979 Daily Chemistry Logs, July 1 - August 1, 1979 Completed records issued for control of LCO's for Operating Equipment (A-52.4) during the period June
July 25, 197 (2)
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; and, Problem identification reports confirm compliance with TS reporting and LCO requirements.
(3)
Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifications and the following procedures:
A-17, "Plant Operations Review Committee Operating Procedure,"
Revision 25; A-20, "Control Room Logs," Revision 8; A-25, "Reporting of Unusual Plant Conditions," Revision 7'-25..1,
"Ginna Station Event Report," Revision ll; A-46, "Bypass of Safety Function and Jumper Control,"
Revision 4; A-52.2, "Control of Locked Valve Operation," Revision 28; A-52. 1,, "Shift Organization, Relief and Turnover,"
Revision 5; A-52.4, "Control of Limiting Conditions for Operations,"
Revision 16; A-52.5, "Control of Limiting Conditions for System Specifications,"
Revision 4; A-52.6, "Operations Standing Order," Revision 3; A-52.7, "Operations Plan," Revision 1; and, No items of noncompliance were identifie b.
Plant. Tour (1)
The inspectors conducted tours of the plant areas listed below at various times during the inspection to observe the status of plant systems and conditions and to observe activities in progress.
Additionally, the inspectors observed Control Room activities and plant systems status periodically during the inspection.
The plant areas inspected were:
Auxiliary Building, Intermidiate Building, Turbine Building, Spent Fuel Pool Area, Safeguard Pump Area, Main and Auxiliary Feed Pump Areas, Relay Room, Diesel Generator Rooms, and Screenhouse.
The following observations/determinations were made:
Control Room and local monitoring instrumentation were observed to confirm. proper calibration status and/or confirm compliance with Technical Specification requirements.
The items examined included:
Spent Fuel Pool temperature, RCS System flow, pressure and temperature, level and temperature indication for boric acid storage tanks, and various control board indications;.
Radiation 'controls were observed in Controlled Areas including posting of radiation areas, Radiation and Special Work Permits in use, condition of'tep off pads, and disposal of protective clothing; Plant housekeeping conditions were reviewed to observe general cleanliness and,to detect the pressence of hazardous conditions; Hydraulic snubbers and pipe hangers were observed for proper settings and oil. levels; Control Room manning and shift turnovers were observed on several occasions during the inspection; Piping in areas toured was observed for existence of fluid leaks and piping vibration; Discussions were conducted with control room operators on several occasions pertaining to the reasons for selected. lighted announciates; Fire extinguishers, hose stations and alarm stations were observed for posting, condition and personnel obstructions; and;
Designated
"no smoking" areas were observed for evidence of smoking, (2)
Acceptance criteria for the above items included inspector judgement and requirements of 10 CFR 50.54(K), Regulatory Guide 1..114, applicable Technical Specifications and current'evision of the following procedures:
A-l, Radiation Control Manual, A-S, Safety Committee, A-54.2, Ginna Station Staff Responsibilities for Fire Prevention, OSO C-77-8, Cleanup Station,
. A-52.2, Control of Locked Valve Operation,
'A-36, Station Holding Rules, A-48, Test Tag Control Program, A-54, Ginna Station Adminstrative and Engineering Staff Responsibilities, A-54.4, Duty Engineer Responsibilities, 0-6, Operation and Process Monitoring, and,
. A-52.1, Shift Organization, Relief, and Turnover.
(3)
Except as noted below, the inspector had no comments regarding the above observations.
(a)
During the tours, the inspector identified the following minor discrepancies:
A temporary gage on the B SI Pump seal water line was observed to have a slight leak resulting in accumulation of acid 'crystals; and, A bottle of rust remover was found unattended in the vicinity of the spent fuel pool.
These items were identified to the licensee and were corrected prior to the end of this inspectio r (b)
During this inspection, the inspectors periodically observed plant operations.'associated:with:heatup from cold shutdown and preparations for reactor startup.
As part of these observations, the inspector selectively confirmed compliance with appropriate Technical Specification (TS) requirements for the initiation of plant heatup, maintenance of plant conditions, and preparations for reactor critical ity including:
TS 3.1.1, Conditions for-starting RCP's; TS 3;1.2, Minimum RCS Pressure-Temperature (NDIT)
Limits; TS 3.2, ECCS System Operability; TS 3.5, NIS Surveillance Requirements; TS 3.1.2, Heatup Rate (RCS) Limits; TS 3.1.6, RCS Chemistry; TS 3.1.4, Secondary Coolant Activity; TS 3. 2, RWST Level 5 Boron Concentration; TS 3.2, BAST Level, Temperature 8 Boron Concentration; and, TS 3.1.6, RCS Activity..
The inspectors also reviewed the procedures associated with the above plant evolutions in order to determine whether the applicable procedures were utilized to complete the evolutions, whether documentation of proper procedure performance was present, and whether procedures for upcoming evolutions were aVailable.
The following completed or in-process procedures were reviewed:
0-1.1, Plant Heatup from Cold Shutdown to Hot Shutdown, Revision 18 (in progress);
0-1.1B, Establishing Containment Integrity, Revision 18 (Completed 8/1/79);
0-1.1C, PrecriticalTechnical Specification Check Sheet, Revision 18 (To be completed);
0-1.1D, Preheatup Plant Requirement Checklist, Revision 7, PCN 79-1614 (completed 8/1/79);
0-1.2 Plant from Hot Shutdown to Steady Load, Revision 49, (to be completed);
0-1.2.1, Yn Curves, Revision 1 (to be completed);
0-1.2.2, Critical Rod Position Calculations, Revision 16,, (to be completed);
0-7, Alignment and Operation of the Reactor Vessel Overpressure Protection System, Revision 4 (completed August 2, 1979 for removal for service);
A52.2, Control of Locked Valve Operation, Revision 28; S-1A, Startup of Rod Drive MG Sets, Revision 3,.
(to be completed);
S-3.1B, Preoperational'ineup of Boric Acid, Revision 8, (completed 7/29/79);
S-3.1D, Boron Control Valve Lineup, Revision 2, (completed 7/29/79);
S-12.1, Leakage Detection Systems Pre Startup, Revision 1, (completed 7/30/79);
S-13A, RHR System Lineup for Safety Injection, Revision 13, (completed 8/2/79);
S-16A, Safety Injection System Alighment, Revision 16, (completed.8/1/791; S-17.1, Containment Spray System, Revision 3, (completed 7/31/79);
S-23.1, 1A Containment Recirculation Fan Cooler Prestartup, Revision 0, (completed 8/1/79);
S-23.3, IC Containment Recirculation Fan Cooler Prestartup,.
Revision 0, (completed 8/1/79);
S-23.4, ID Containment Recirculation Fan Cooler Prestartup, Revision 1, [completed 8/1/79);
T-36.1, Station Service Mater - Heater Valve Alignment for Two Loop Operation, Revision 2, (completed 7/25/79);
T-41A, Alignment of Auxiliary Feedwater System Prior to Power Operation, Revision 15, (completed 8/1/79);
T-55.2, Standby Auxiliary Feedwater System Alignment for Normal Operation, Revision. 2, (completed 8/1/79);
PT-6.1,. Source Range Nuclear Instrumentation System Channel N31, Revision 11,, (completed 7/31/79);
PT-6.1, Source Range Nuclear Instrumentation System Channel N32,- Revision ll, (completed 7/31/79);-
PT-6.2, NIS Intermediate Range Channel N35, Revision 9, (completed 7/31/79);
PT-6.2, N15 Intermediate Range Channel N36, Revision 9, (Completed 7/31/79);
PT-6.3.1, Power Range N15 Channel 41, Revision 11, (completed 7/31/79);
PT-6.3.2, Power Range N15 Channel 42, Revision ll, (completed 7/31/79);
PT-6.3.3, Power Range N15 Channel 43, Revision 10, (completed 7/31/79);
'PT-6. 3.4, Power Range N15 Channel 44, Revision ll, (completed 7/31/79);
PT-ll, 60.Ce'll Battery Banks A8B,;Revision.8;:(completed 7/25/79);
PT-12. 1, Emergency Diesel Generator, 1A, Revision 10, (completed 7/5/79);
PT-12. 2, Emergency Diesel Generator 1B, Revision ll, (completed 7/12/79);
and, PT-17.2, Process Radiation Monitors R-ll through R-21 and Iodine Monitors R-10A and R-10B, Revision 29, (completed 7/23/79).
No items of noncomplian'ce were identifie Review of IE Bulletin 79-02, Revision 1, Pi e
Su ort Base Plates Uti izin Concrete Ex ansion Bo ts a.
Introduction The subject. IE Bulletin was issued June 21, 1979.
It required the -conduct of a testing program, if sufficient documentation was not.available to confirm that the minimum design requirements were met for installed pipe support based plates utilizing concrete expansion bolts.
The licensee informed Region
on July 6, 1979
,- that sufficent documentation did not exist to verify that anchor bolt design requirements were met; and, that a testing and replacement program was initiated to verify the design function of the aforementioned base plates.
The licensee informed Region I on July 26, 1979, that the testing and replacement program for, both accessible and inaccessible base plates in.Phase I systems or portions of systems (defined in the supplemental response)
was to be completed by August 1, 1979.
The inspector's review of this
'atter was directed toward establishing that the program had been substantially completed utilizing testing and installation procedures consistent with the IE Bulletin.
This was performed by:
Genera'l sampling review of testing and installation records to verify that base plates in Phase I systems were incorporated as appropriate (Note:
the completeness of the program was not confirmed during this review)
Review of testing specifications and procedures; Review of installation specifications and procedures; Review of selected re'cords associated with specific supports for consistency with testing/installation requirements.
No items of noncompliance or deviations were identified during this review.
However, the adequacy of the analytic approach (base plate flexibility, factors of safety, cyclic load considerations)
and the testing/repair procedures is being reviewed by NRC management.
Therefore, this area will remain open and will be reinspected (79-BU-02).
The results of the procedure and data review are discussed belo b.
Rev'iew of Testin and Re air Procedures The inspector reviewed. the below listed references and verified that they incorporated the following:
all anchors were identified as to type with diameter and specified-embedment depth; b'ase plate..size, bolt hole. size, centerline distance between
, bolt. ha]qs qnd.centerl.one distance'etween bolt hole and plate edge were to.be measured and documented; the minimum embedment depth was consistent with manufacturer's data (checked for Hilti Kwik Bolts);
the minimum thread engagement was defined as "protruding above the nut";
base plate to surface gaps were to be measured and documented; the presence of leveling nuts was to be checked and documented; the torque valves were. specified; embedment during testing was measured utilizing ultrasonic testing; and, measuring the concrete to top of the stud distance and comparing it to the stud length specified on drawings; embedment subsequent to repair was determined by verification of.stud length prior to installation and measurement of concrete surface to stud protrusion subsequent to installation; thread engagement was checked subsequent to repairs; preload was achieved utilizing calibrated (daily) torque wrenches and final torque was to be witnessed and documented by QC; and, verification that the anchor nut had not bottomed out was required.
The references reviewed were:
ME-129, Technical Specification for. Inspection Requirements for Wedge Type Expanison Anchors, Revision 1, July 13, 1979; ME-130, Technical Specification for Concrete Anchor Bolt Replacements and Pipe Supp'ort Modifications, Revision 2, July 14, 1979;
c ~
gV-ME-130, guality Verification Specification, Inspection and Testing Requirements for Concrete Anchor Bolt Replacement and Pipe Support Nodification, Revision 2, July 14, 1979; ISI-9, Inservice Inspection of Hedge Type Anchor Bolts, Revision 1, July 10, 1979; EHR-2441-2, Work Procedure for Anchor Bold Replacement and Pipe Support Rework, Revision.0, July 15, 1979; and EH-233, Rework of Pipe Supports, Base plates, and Anchor Bolts-, Revision 0, July 9, 1979.
Data Review The inspector did not witness any testing/repair activities since the work had been completed prior to the coranencement of the inspection.
A preliminary review of the testing and repair records was conducted to verify general compliance with the references listed above.
No items of noncompliance were identified.
5..
Review of IE Bulletin 79-13 and Licensee Event Re ort 79-13/01T, Crac in in Fee water Lines The subject IE Bulletin was issued on June 25, 1979 and required licensees to conduct inspections of feedwater piping similar to that which had experienced cracking at other facilities.
The Ginna Station shut down on July 6, 1979, to accomplish these inspections.
The licensee informed Region I on July 11 that. indications of cracking had been identified in both steam generator's nozzle-to-feedwater piping weld joints and. that repairs were in progress.
Since that time, the licensee has completed the inspections required by the bulletin and has repaired and retested the welds above.
No other deficiencies requiring repair have been identified during the inspections.
The inspector reviewed the licensee submittals to NRC, inspection procedures and records, and repair procedures and records in order to determine that:
Required.radiographic and supplementary ultrasonic examinations of feedwater system welds had been performed arid the results documented and evaluated; An expanded inspection program was implemented as required by the bulletin based upon detection of cracking described above; Visual inspections of feedwater system piping supports were conducted to verify operabi lity and conformance to design requirements;
Auxiliary feedwater'iping to main feedwater piping welds were examined for cracking; Required reports to NRC had been prepared, submitted, and appeared to accurately describe the licensee's inspection findings and corrective action; and, Reviews of operating and emergency procedures and system features had been conducted to ensure their adequacy for detecting and responding to feedwater line. break accidents.
The inspector's review was directed at determining whether each of the above items had been addressed by the licensee and whether each activity appeared to have been accomplished in accordance with established procedures.
The inspector did not review the licensee s activities with respect to compliance with industry codes and standards applicable to the'welding and nondestructive examination performed.
This review will be accomplished during future inspections and this item will rema, in open pending completion of those reviews by NRC:RI (79-BU-13).
The following documents were reviewed in respect to the items listed above:
Licensee Event Report No. 79-13, s'ubmittals dated July 11 and 23, 1979; RG&E Responses to IE Bulletin 79-13, submittals-dated July 12 and 27, 1979; Inservice Inspection Procedure ISI-8, Inservice Inspection of Feedwater Nozzle Welds, Revision 1, Completed August 1, 1979, including associated inspection data; Emergency t1aintenance Procedure EM-232, Repair of Feedwater Pjpjng Inside Containment, Revision 0, completed for both Steam generators including inspection data; Emergency.Procedure E-29. 1, Loss of Normal Feedwater (Not Recoverable),
geyisjon',
issued July 17, 1979; Emergency Procedure E-1.3, Steam Line Break Accident, Revision 4, issued June.13,.1979; Reactor Plant Operation Procedure S-12. 1, Leakage Detection System Prestartup,
.Revision 1, issued July 1, 1977; Reactor Plant Operation Procedure S-12.2, Oeprator Action in the Eyent of Indication of a Significant Increase in Leakage, Revision 5, issued April 14, 1977; and,
Reactor Plant Operation Procedure S-12.3, Operator Action for Significant Leakage which Cannot Be Located, Revision 1, January 4, 1978.
No items of noncompliance were identified.
6.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on August 3, 1979.
The inspectors summarized the scope and findings of the inspection.
The licensee acknowledged the transfer of lead responsibility for the NRC:RI inspection and enforcement activities at the R.
E. Ginna station from Mr.
D.
Beckman to Mr.
R. S. Markowski.