IR 05000244/1978018
| ML17244A177 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/05/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17244A176 | List: |
| References | |
| 50-244-78-18, NUDOCS 7810180179 | |
| Download: ML17244A177 (30) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Docket No. 50-244
. ~R-1 Priority Category Licensee:
Rochester Gas and Electric Cor oration 89 East Avenue Rochester New York 14649 Facility Name:
R.
E.
Ginna Nuclear Power Plant, Unit
Inspection at:
Ontario, New York Inspection conducted:
August 14-18, 1978 Inspectors:
M. J.
Raym d,
Re ctor Inspector
/gWrgZ8 date signed R.
M. Knoll -Reactor Ins ector Co-op date signed Approved b
R.
R. Kei g, Chief, Reactor Projects Section No. 1, ROMANS Branch date signed date signed Ins ection Summar
Ins ection on Au ust 14-18, 1978 Re ort No. 50-244/78-18 d:
,
d
1
Ry
1
d 1 *1 started on a backshift, of plant operations including logs, records, plant status and a tour of the facility; the status of previous inspection findings; operability, performance and conformance of the chemical and volume control system with Technical Specification requirements; and, licensee followup actions on IE Circulars and Bulletins.
The inspection involved 36 inspector hours onsite by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
7 tl0 ~ 8
DETAILS Persons Contacted Mr. T. Alexander, Head Control Operator
- Mr. H. Backus, Operations Supervisor
- Mr. S. Bullock, guality Control Engineer Mr. L. Depew, Shift Foreman Mr. C. Edgar, Instrument and Control Foreman
- Mr. D. Gent, Results
& Test Foreman Mr. P. Gorski, Auxiliary Operator
- Mr. D. Hamelink, Maintenance Supervisor Mr. R. Junot, Shift Foreman
- Mr. G. Larizza, Technical Engineer Mr. R. Latz', Electrical Foreman Mr. T. Marlow, Cadet Engineer Mr. J.
Noon, Assistant Superintendent Mr. C. Pgck, Operations Engineer Mr. T. Rhkiewicz, Instrument and Control Technician
- Mr. B. Snow, Superintendent
- Mr. S. Spector, Maintenance Engineer Mr. T. White, Auxiliary Operator The inspector also 'nterviewed other licensee employees during the course of the inspection, including members of operations, health physics, maintenance, and general office staff.
- denotes those present at the exit interview.
'Status of Previous Ins ection Findin s (Closed)
Noncompliance (244/78-04-01):
Hold Log and Tagging Control.
PCN 78-442 was issued for A54.4 on March 28, 1978, to require a
spot check of outstanding
"Holds" during the weekly facility tour by the duty engineer.
The inspector noted that the weekly check was documented in the completed A54.4's reviewed during this inspection, as listed in detail 3.b of this report.
PCN 78-1002 was issued for A-36 on May 25, 1978 to provide additional controls to ensure positive identification and documentation of tag removal operation (Closed)
Unresol ved Item (244/78-17-03):
Action for IEB 78-04.
RGSE memoranda dated February 27, 1978, were provided for inspector review to document the licensee's actions in regard to IEB 78-04.
The inspector noted that procedure E-l.l, SI System Actuation, was used to conduct the subject review and provides a listing of those plant system. valves that receive an "SI" or "T" signal during an accident sequence.
The inspector used procedure E-l.l in conjunc-tion with system elementary drawings to confirm, on a sampling basis, the licensee position on stem mounted limit switches.
Further information on this item is provided in detail 5 of this report; (Closed)
Noncompliance (244/78-11-01):
Calibration of Diesel KW
~ Meters.
CAR 78-1191 was completed on July 10, 1978 to accomplish-the following:
(i) CP's 502.1 and 502.2 were issued for use on May 19, 1978 to provide for diesel generator KW meter calibration; (ii)
the subject meters were calibrated using the above procedures on May 19, 1978; and, (iii) PCN 78-1369 was issued on July 17, 1978 to incorporate into Administrative Procedure A-60.3 the requirement for periodic calibration of the meters.
The inspector had no further questions at this time in regard to action taken.
The inspector noted, however, that no action had yet been initiated concerning a review of plant equipment calibration requirements, as stated in the licensee's July 19, 1978 response to NRC:RI.
The licensee stated that the intent of the position taken in the July
'19, 1978 letter was to have representatives from the onsite Results and Test Group work with Ele'ctric Meter and Laboratory Department (EMLD) personnel in a review of calibration requirements of the plant Technical Specifications for components associated with safety related systems to assure all necessary calibration procedures are provided.
The licensee stated that this review would be initiated by September 15, 1978 and would require several months to complete.
The inspector stated that this item would be unresolved pending completion of the subject review and subsequent review by the NRC (244/78-18-01).
Review of Plant 0 erations a.
Shift Lo s and Ooeratin Records The inspector reviewed the following logs and records:
Official Record; June 1 - August 14, 197 Date Shift Foreman Record; June 1 - August 14, 1978.
Auxiliary Operator's Primary Side Log; June 14 - August 14, 1978.
Auxiliary Operator's Secondary Side Log; June 14 -August 14, 1978.
Operations Plan Ginna Station; June 1 - August 14, 1978.
Bypass of Safety Function and Jumper Control Requests; 78-26 (June 14, 1978) through 78-29 (July 20, 1978).
Completed Ginna Station Event Reports (A-25.1)
for events which occurred during the period March 29 -July 24, 1978.
Completed records issued for control of LCO's for opera-ting equipment (A-52.4) during the period March 27 - July 18, 1978, as described below.
Affected E ui ment 5/1/78 5/2/78 5/3/78 5/10/78 5/26/78 5/26/78 5/26/78 6/7/78 6/8/78 6/16/78 6/29/78 A,Charging Pump Packing Gland A
SW Pump Expansion Joint C
SW Pump Expansion Joint B
Containment Recirculation Fan Bearing AKC SW Pump Intake Screens Engine Fire Pump Intake Screen Motor Fire Pump Intake Screen A, B, C, D
SW Pump Motor Inspection C Charging Pump Belt Diesel Fire Pump Breather Cap Motor Fire Pump Preventative Maintenance
6/29/78 Diesel Fire Pump Preventative Maintenance 6/29/78 860B Valve 7/7/78 Main Steam Line Snubbers, MS146B Top and Bottom 7/18/78 C Charging Pump Packing Gland (,NOTE'he During this same period, there were no records issued for the control of limiting conditions for system specifications (A-S2.5).}
OSO-C-78-3, "List of gualified Personnel Authorized to Accompany and Assist the Acting.'Station Holding Authority'n Effecting or Removing a Hold," August 3, 1978.
OSO-C-78-8,
"Cleanup Stations,"
June 19, 1978.
S-12.2, RCS Leakage Evaluation Instructions for the following dates:
June 1, 2, 9, 12, 18, and 19, 1978, July 18 and 19, 1978, and August 3, 1978.
Outstanding Ginna Station Maintenance Work Order and Trouble Reports on a sampling basis for reports dating back to 1973.
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 Technical Specifications (TS).
Jumper log entries do not conflict with TS.
Problem identification reports confirm compliance with TS reporting and LCO requirement 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 Pro-cedure, Revision 19.
A-20, "Control Room Logs", Revision 6.
A-25, "Reporting of Unusual Plant Conditions," Revision 7.
A-25.1, "Ginna Station Event Report," Revision 11.
A-46, "Bypass of Safety Function and Jumper Control,"
Revision 4.
A-52.2, "Control of Locked Valve Operation,"
Revision 21.
A-52.1, "Shift Organization, Relief and Turnover," Revision 4.
A-52.4, "Control of Limiting Conditions for Operations,"
Revision 12.
A-52.5, "Control of Limiting Conditions for System Speci-fications, Revision 4.
A-52.6, "Operations Standing Order," Revision 3.
A-52.7, "Operations Plan," Revision l.
gC 1701, "guality Assurance Records,"
Revision 9.
No items of noncompliance were identified and except as noted below, the inspector had no further questions in this area.
During the review of Ginna Station Work Order and Trouble Reports, the inspector noted that a relatively large number of work orders (estimated at several hundred by the inspector)
were outstanding and dated back to 1973.
The inspector conducted a sampling review of work orders maintained in the Shift Foreman's office to ascertain the nature, importance and status of the outstanding items.
The fin'dirigs are as follows:
(a}
A substantial number of the work orders were non-safety related and could be closed out within an indefinite time period; (b)
Some work orders, which could not be considered to pose an immediate threat to plant or personnel safety, involved items which nevertheless were significant and should receive more management attention to assure a timely close-out;
,(c}
Some of the work orders listed as outstanding were found to be completed, indicating that work order forms are not being cleared when maintenance is finished.
The licensee stated that a comprehensive review of the Work Order and Trouble Report system will be completed to (i} evaluate and reassign priority to close important items, and (ii) update the file to assure it reflects an accurate completion status.
The licensee stated that this review would be completed by November 31, 1978.
This item is unresolved pending completion of the licensee's actions and subsequent review by the NRC (244/78-18-02).
(2}
The station event report (A25.1) issued on April 7, 1978 concerned potential leakage in Service Water System loop
"A" piping.
The portion of the loop "A" header affected is located underground between the auxiliary building and the intake structure and is bounded by system valves 4623, 4665,, 4605 and 4606 (reference:
system drawing 33013-529).
The potential leakage was identified during a system hydro test conducted during the last refueling outage.
Initial testing on April 6, 1978, with the
=
system aligned according to RSSP-13.8, indicated system leakage at about 8 gpm under a 60 psig hydro test pressure.
Subsequent testing on May 9, 1978,.with the test boundary reduced (as described above) to pinpoint the problem, resulted in a measured leakage of 3.33 gpm at a hydro test pressure of 165 psig.
RSSP 13.8 test requirements were met with the attainment of a 165 psiq hydro test pressure and no further testing was performed during the outag Licensee review and evaluation of this item are docu-mented in WR 78-785, PORC meeting 45-78 and PAR 20-78.
The PORC has determined that the ability of the service water system to meet its design requirements has not been impaired.
Further investigation is planned to determine if leakage is through test boundary valves or underground piping.
(Several potential leakage paths through test boundary valves were identified after the May 9 test.)
The licensee noted that during interim plant operations, any degradation in service water system performance will be detected through routine surveillance testing.
The inspector had no further questions at this time on the licensee's actions to resolve the hydro test results.
However, this item is unresolved pending completion of the licensee's. investigations in this area and subsequent review by the NRC:
RI (244/78-18-03).
b.
Plant Tour The inspector conducted tours of the accessible plant areas listed below at various times during August 14-18, 1978 to observe the status of plant systems and condi tions and to observe activities in progresss.
Additionally, the inspector observed Control Room activities and plant system status at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on August 14, 1978.
The plant areas inspected were as follows:
Auxiliary Building, Intermediate Building, Turbine Building, Diesel Rooms, Battery Rooms, Safeguard Pump Area, Main and Auxiliary,Feedwater Pump Areas, Cable Tunnel, Switch-
.gear Rooms, Intake Structure, and a walkdown of the security perimeter.
The following observations/determinations were made:
Radiation controls established by the licensee, including posting of radiation areas, radiation work permits in use, the condition, of step off pads, and the disposal of protective clothing were observed.
Actual radiation levels present at various locations in the auxiliary building were measured and compared to posted value Control Room and local monitors were observed to verify.
plant operation in conformance with Technical Specification LCO requirements.
Items examined included:
refueling water storage tank level and boron concentration; accumu-lator pressur'e, level, and boron concentration; spray additive tank volume and sodium hydroxide concentration; boric acid storage tank level, boric acid concentration, and temperature; condensate storage tank level; nuclear instrumentation; diesel generator start controls; control rod position indication and insertion; reactor coolant system operating parameters, including pressure, tempera-ture, power, offset, total flow, and boron concentration; temperature indications for boric acid heat tracing; and diesel fuel oil levels.
Plant housekeeping conditions were reviewed to observe general cleanliness and to detect the presence of hazardous conditions.
Systems and equipment in all areas toured were observed for the existence of fluid leaks and abnormal vibrations.
Hydraulic snubbers and pipe hangers were observed for proper conditions.
The control board was observed. for annunciators that should not be lighted during the existing plant conditions.
Overall plant status was discussed with a control operator.
The locked valve log book was reviewed for the period April 27 to August 16, 1978.
There were no new entries during this time.
During the course of this review, the inspector verified pr oper positions for 62 valves in the Safety Injection, Residual Heat Removal, Chemical and Yolume Control, Auxiliary Feed Water, Service Water, and Containment Spray. Systems:
313, 331,'34, 338, 341, 345, 347, 348A, 348B, 354, 813, 814, 825A, 825B, 826A, 826B, 826C, 826D, 836A, 836B, 841, 850A, 850B, 851A, 8518, 852A, 852B, 856, 857A, 857B, 857C, 860A, 860B, 860C, 860D,, 865, 878A, 878B, 878C, 878D, 896A, 896B, 3516, 3517, 4007, 4008, 4027, 4028, 4269, 4270, 4271, 4272, 4344, 4345, 4561, 4562, 5871, 5872,.5873, 5874, 5875, 587 RGSE Hold Log entries were reviewed for the period June 12 to August 14, 1978.
Selected equipment hold tags were observed for proper posting and tagged equipment was reviewed for proper positioning.
The following tags were reviewed:
77-2366, 78-1403, 78-1404, 78-1761, 78-1875, 78-1876.
The licensee's policy and practice regarding plant tours was.reviewed; there were no changes in this area.
Outy Engineer Tour findings documented in procedure A-54.4 completed April 21 to July 31, 1978 were reviewed.
Control room manning was observed on several occasions during the inspection.
Control room operators were knowledgeable of existing plant conditions and equipment status.
The source range NI 31 and 32 test results completed in accordance with PT 6.1 on August 14, 1978 were reviewed.
The inspector noted that procedural requir'ements were completed as required and that all readings were within speci fied 1 imits.
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 the following procedures:
A-l, "Radiation Control Manual," Revision 9.
A-5, "Safety Committee, Revision 3.
A-54.2,
"Ginna Station Staff Responsibilities for Fire Prevention,"
Revision 1.
OSO C-77-8, Cleanup Stations,"
dated January 18, 1978.
A-52.2, "Control of Locked Valve Operation,"
Revision 16.
A-36, "Station Holding Rules," Revision A-48, "Test Tag.Control Program," Revision 4.
A-54,, "Ginna Station Administrative and Engineering Staff Responsibilities,"
Revision 6.
A-54.4, "Duty Engineer Responsibilities,"
Revision 6.
0-6, "Operation and Process Monitoring," Revision 15.
A-52.1, "Shift Organization, Relief, and Turnover,"
Revision 3.
Except as noted below, no discrepancies were found in the above areas.
The inspector witnessed the performance of PT-12.2, Emergency Diesel Generator 1B Test, Rev.
8 on August 16, 1978.
The inspector verified that the procedure was available and in use by test personnel, pre-start align-ment operations were completed using T-27.2 and data were taken as required by the procedure.
During the initial test run, the 1B diesel was started and tied onto the No.
17 bus satisfactorily.
When the No.
16 bus tie br'eaker was closed, the No.
16 bus breaker DC control power was lost.
Attempts to trip the breaker manually'were not successful.
Subsequent investigation by the licensee revealed that the DC control fuses had blown when the No.
16 bus breaker was closed and that the fuse holder stabs were bent slightly to prevent good contact.
After replacing the fuses and straightening the holder stabs, the breaker was closed and tripped successfully three times in the test position and a 30 minute run of the 1B diesel loaded to 1800 KW was satisfactorily completed.
The ability of the 1B diesel to load the No.
16 bus under an ES condition'had not been affected.
The loss of DC control power to the breaker disabled diesel trips except for engine overspeed and overcurrent.
The overcurrent trip, in particular, was operable and capable of pro-viding diesel protection.
(The inspector noted that most diesel trips are bypassed in the emergency mode.)
(2)
(3)
The licensee stated that a 30 day report would be submitted to the NRC to document this event and to describe any other finding/corrective actions deemed necessary pursuant to further followup reviews.
This item is unresolved pending receipt and subsequent review of the licensee's report (244/78-18-04).
As a result of the inspector's review of. outstanding work orders (reference detail 3.a above),
a walkdown of the security fence was completed to observe a problem identified in work order 78-1878.
The condition described by the subject work order was found to be corrected on August 16, 1978.
During the inspector's tour, five other problem areas were identified which, while not constituting. a degradation of the security perimeter, warranted followup action by the licensee.
The licensee noted the inspector's findings and initiated corrective actions.
This item will be followed on a subsequent inspection (244/78-18-.
OS).
Upon arrival of the inspector at the site at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on August 14, 1978, the licensee reported that the bo'dy of a male caucasion was found on the shore of Lake Ontario, on RGKE controlled property.
The bo'dy was discovered during a routine fire watch inspection tour conducted in the afternoon of August 14.
The body had apparently been in the water. for an extended period of'ime.
The local law enforcement agency was contacted and has assumed responsibility for the investigation.
There was no apparent threat to site security.
The inspector had no further questions regarding this matter.
4.
CVCS Review The inspector conducted a review of the Chemical and Volume Control System (CVCS) to verify that current system status and past performance were in compliance with applicable Technical Specification limiting conditions for operation and limiting safety system settings.
The following were reviewed for the purposes of this system audit:
(a)
CVCS System Description dated June, 1976.
(b)
RG&E Ginna Station gA Manual, Appendix A, Rev.
1, dated October 15, 1976, CVCS Engineering Flow Diagrams Nos.
33013-426-D, 33013-427, 33013-433-A and 33013-434.
(c).
RG&E Technical Specifications, Appendix-A, Items 2.2, 3.1.5, 3.1.6, 3.2, 3.1.4 and Table 4.1-1.
(d)
S-12.2, RCS Leakage Evaluation Instructions, for selected evaluations conducted in the period of June - August, 1978.
(e}
A-25.1's, Station Event Reports, issued, for the period of March -July, 1978.
(f)
A-52.4's, Control, of Limiting Conditons for Operation, issued for the period of. March - July, 1978.
(g)
RCS and auxiliary system chemistry logs for the month of August, 1978.
This review included a walkdown of selected portions of the CVCS system to observe:
proper valve positioning which provides three separate boron injection flow paths to the RCS, as required by TS 3.2; proper conditions on. pipe supports, hangers and snubbers; status of local and remote control panels; operability of following instrumentation-LT 139B, LT 139A, LT 112, and the RCS letdown radiation monitor;,and, general system conditions.
No items of, noncompliance were identified.
5.
IE Bulletin and Circular Followu The. inspector reviewed the licensee's actions regarding the IE Bulletins and Circulars listed below:
IEB 77-04, Calculational Error Affecting the Design Performance of a System for Controlling pH of Containment Samp Water Following a LOCA.
IEB 78-04, Environmental gualifications of Certain Stem Mounted Limit Switches Inside of Reactor Containmen IEC 77-10, Vacuum Conditions Resulting in Damage to Liquid Process Tanks.
IEC 77-11, Leakage of Containment Isolation Valves with Resilient Seats.
IEC 77-14, Separation of Contaminated Water Systems From Non-contaminated Plant Systems.
IEC 77-15, Degradation of Fuel Oil Flow to the Emergency Diesel Generator.
IEC 77-16, Emergency Diesel Generator Electrical Trip Lock-Out Features.
The review was conducted to verify that:
copies of the bulletin/circular were forwarded.to the appropriate onsite management; the licensee's reply to the bulletin was prompt and within the specified time period; information discussed in the licensee's response was supported by facility records; and, the licensee's corrective actions, if required, were appropriate as described in his response.
A review of the following supportive information was completed:
Licensee response to IEB 77-04, dated December 21, 1977.
Licensee response to IEB 78-04, dated March 3, 1978.
RGSE internal memorandum, dated October 12, 1977, regarding containment isolation values.
Preventative Action Report (PAR) 78-77, dated September 9,
1977, regarding containment isolation valves.
Correction Action Report (CAR)109-77, dated December 8, 1977, regarding interties between contaminated and noncontaminated plant systems.
RG&E internal memorandum dated December 29, 1977, regarding diesel fuel oil supply lines.
PAR 112-77, dated December 21, 1977, regarding diesel fuel oil suppl PAR 114-77, dated June 19, 1978, regarding diesel trip lockout features.
PAR 7-78, dated February 27, 1978, regarding limit switches on safeguard and isolation valves.
RG&E internal memorandum dated February 27, 1978, in response to Westinghouse Technical Bulletin NSD-TB-77-13.
Procedure El.l, Safety Injection System Actuation, Rev. 5, January 24, 1978.
Elementary drawings and electrical schematics for MOVs 826A, 826C, 878B, 878D, 852A, 852B, 841, 865, 1815A and 1815B, and for AOVs 371, 951, 953, 955, 1728, 1723, 5738, 5737, IV3, IV5 and IVI.
No items of noncompliance were identified.
6.
Unresolved Items Unresolved items are those items for which more information is required to determine if the items are acceptable or items of noncompliance.
Unresolved items are listed in details 2 and 3 of this report.
7.
Exit Interview A management meeting was held at the site with'licensee personnel (identified in detail l),on August 18, 1978.
The purpose, scope and findings of this inspection were discussed as they appear in the details of this repor