IR 05000244/1978021
| ML17261A098 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/22/1978 |
| From: | Foley T, Raymond W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17261A097 | List: |
| References | |
| 50-244-78-21, NUDOCS 7901080240 | |
| Download: ML17261A098 (32) | |
Text
Report No.
Docket No.,
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I N.~
Pi ly Licensee:
c e ter Gas and Electric Cor oration Category 89 East Avenue Rochester New York 14649 Facility Name:
R.
E.
Ginna Nuclear Power Plant, Unit
Inspection at:
Ontario, New York Inspectors:
Inspection conducte
October 23-27,
47 W.
Ra ond, Rea r In e
T. Foley, Rea or Inspector ra>nee i~ ~l 73 ate signed u/WS date signed Approved by:
R.
R.
eimig ie
,
eac or rogects Section No. 1, RO Branch date signed rl"zz-s date signed Ins ection Summar
Ins ection on October 23-27, 1978 Re ort No. 50-244/78-21 A~t: R, p
y gi 1b*di p
of plant operations, started on a backshift, including facility logs; records and plant status; status of previous inspection findings; rework of pressurizer splice insulation; changes to the licensee's organization; in-office review of
- LERs; on-site LER followup; licensee action on circulars and bulletins; and, periodic and special reports submitted by the licensee.
The inspection involved 70 inspector hours on site by one NRC regional based inspector and one inspector trainee.
Results:
No items of noncompliance were identified.
V90i.GSe~gc Region I Form 12 (Rev. April 77)
DETAILS 1.
Persons Contacted
- Mr. M.
- Mr. S.
Mr. C.
Mr.
D.
Mr. R.
- Mr. J.
- Mr. B.
Mr. S.
Backus, Operations Supervisor Bullock, guality Control Engineer Edgar, I&C Foreman Horning, Shift Foreman Morrill, Training Coordinator Noon, Assistant Plant Superintendent Snow, Plant Superintendent Spector, Maintenance Engineer The inspectors also interviewed other licensee employees during the course of the inspection, including members of the operations, health physics, maintenance, quality control and general office staff.
- denotes those present at the exit interview.
2.
Licensee'Action on Previous Ins ection Findin s
(Closed)
Noncompliance (244/77-04-01):
Modified Spent Fuel Pool Locations.
The inspector reviewed the licensee's corrective actions in regard to the spent fuel pool modification.
A plug
.
for the 596th storage location (position H-1) was observed to be installed as required.
EPM No.
gE314G, Rev.
1 dated August 23, 1977, steps 3.1.2 and 3.1.4, provide additional instructions re-garding design control as described in the May 26, 1977 letter from the licensee.
JAM Section 3, Rev. 7, dated March 1, 1978,
"Configuration Control" incorporates the same requirements.
PDR-0048, dated August 23, 1977, was issued to engineering personnel to describe the changes made to the EPM and to prescribe personnel review of the affected changes.
Internal memorandum dated September 26, 1977 documented that attestation sheets had been received by the gA department from engineering personnel, in acknowledgement of the instructions provided by PDR-0048.
The inspector had no further questions on this ite '
(Closed)
Followup Item (244/78-04-02):
Personnel Changes.
Li-censee changes in organization and personnel were, reviewed and found to be in conformance with applicable requirements, as de-scribed in paragraph 5 of this report.
(Closed)
Unresolved Item (244/77-17-08):
Submittal.
Technical Specification.(TS)
8, 1978 specifies that TS 4. 1 be amended PR NI lower power setpoint prior to each Techni cal Speci ficati on Change Request dated May to require testing of the reactor startup.
(Open)
Unresolved Item (244/77-21-01):
SI Pump Breaker for Bus 16.
CAR 1132 documents the corrective actions taken for circuit breaker DB-50 and is still open.
The inspector reviewed a vendor report dated February 28, 1978 (MIN 236-2411)
which documents the vendor inspection results for the subject breaker.
No anomalies were identified which would have caused the breaker to fail to close.
The inspector stated that this item would remain unresolved pending completion of the licensee's review of the item and satisfactory close-out of CAR 1132.
(Open)
Unresolved Item (244/77-14-07):
Conflicts in Record Re-tention Requirements.
The inspector noted that gC 1701, Rev.
11, dated July 28, 1978 and A-50.5, Rev.
5, dated'pril 12, 1978, still contain conflicting requirements in regard to retention of operator requalification records.
The licensee stated that this item would be readdressed to provide a timely resolution.
(Closed)
Unresolved Item (244/78-20-01):
Rework of Pressurizer Circuits.
Newly installed insulation for the pressurizer circuit splices was reviewed on October 27, 1978 and found to be completed in accordance with vendor installation recommendations.
Additional details are provided in paragraph 4 of this report.
Review of Plant 0 erations a.
Shift Lo s and.0 eratin Records (.1)
The inspector reviewed the following logs and records:
Official Record, August 15 - October
Shift Foreman Record, September 1 - October
Auxiliary Operators Primary Side Logs; August 15-October
Date Auxiliary Operators'econdary Side Logs, August 15 - October
By-pass of Safety Function and Jumper Control Re-quest, (75-31),
(78-25)
and (78-30)
Completed Ginna Station Event Reports (A-25.1) for events which occured during the period August 12-September 6,
1978 Daily Surveillance Log, October '1 - October
Licensee Event Reports, August 12 - September
Operator Plans, August 15 - October
Equipment Running Hours Log, October 23 only Ginna Station Maintenance Work Order and Trouble Reports, Janaury 77 - October
Station Holding Log, September 16 - October
Daily Electrical Log and Generation Log RCS Leakage - Surveillance Logs Locked Radiation Logs Daily Chemistry Logs Completed records issued for control of LCO's for Operating Equipment (A-52.4) during the period July 19 - September 20 as described below:
Affected E ui ment 9/8/78 9/18/78 9/20/78 8/16/78 8/31/78 8/19/78 Containment Recirculation Fan Containment Recirculation Fan RHR Valve (852-A)
B Diesel Bus (Bkr 16)
RHR Valve (Y625)
(2)
Periodic test procedures were reviewed as follows:
PT-9, Undervoltage and Underfrequency Protection llA and 11B and 4160 Volt Bus, Rev. 3, completed September 27, 1978.
PT-6.1, Source Range Nuclear Instrument System, Rev.
11, completed October 23, 1978 PT-17.2, Process Radiation Monitor, Rll-R21 and Iodine Monitors R10A and R10B, Rev.
27, completed September 19, 1978 PT-12.1, Emergency Diesel Generator lA, Rev.
7, completed October S,
1978 PT-20, Main Steam Isolation Valve Solenoid Trip Test, Rev.
2, completed July 20, 1978 (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)
Acceptance criteria for the above review included in-spector judgement and requirements of applicable Technical Specifications and the following procedures:
A-17, "Plant Operations Review Committee Operating Procedure, Revision 2 A-20, "Control Room Logs", Revision 7.
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,"
Re-vision 22.
A-52.1, "Shift Organization, Relief and Turnover,"
Revision 5.
A-52.4, "Control of Limiting Conditions for Opera-tions," Revision 12.
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.
gC 1701, "guality Assurance Records,"
Revision 11.
(5}
No items of noncompliance were identified and except as noted below, the inspector had no further questions in this area.
I (a}
During the review of Ginna Station Work Order and Trouble Reports, the inspector noted that a sub-stantial number of work orders were still outstand-ing, dating back to January 1977.
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 findings are as follows:
(1)
A few of the work orders were non-safety re-lated and could be closed out at any time; (2)
Some work orders, which could not be considered to pose an immediate threat or personnel safety, involved items'which neverthel'ess were signi-ficant and should receive more management attention to assure a timely close-out; (3)
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.
This problem with work orders was identified to the licensee in inspection report 50-244/78-18 conducted August 14-18, 1978, at which time the licensee stated that a comprehensive review of the Work Order and Trouble Report system will be completed to (1)
evaluate and reassign priority to close important items, and (2) update the file to assure it reflects an accurate completion status. 'he licensee stated that this review would be completed by November 31,
'1 978.
(b)
This item continues to be unresolved pending com-pletion of Licensee's actions and subsequent review by the NRC:RI.
During reviews of the shift foreman's log and the official record, many instances of minor discre-pancies (conflicts with Ginna administrative proce-dures)
were noted.
Additionally, several minor discrepancies were noted in procedures PT-17.2, completed on September 19 and October 19, 1978, in that deviations from established limits were not noted in the procedure and corrective actions were apparently not initiated.
Subsequent review of the discrepencies by the inspector identified no technical basis for a safety concern.
However, the inspector expressed concern over the apparent failure to follow-up on deviations from procedural limits and to provide formal (documented)
resolution.
These
items were discussed with the licensee at the exit interview and the licensee indicated that more management attention would be given to this area.
The inspector determined that the discrepancies noted appreared to be isolated instances of problems in the record keeping area.
This item is unresolved pending further review of logs and completed proce-dures 'during subsequent inspections (50-244/78-21-01).
b.
Plant Tour The inspector conducted tours of the accessible plant areas listed below at various times during October 24-27, 1978 to observe the status of plant systems and conditions and to observe activities in progress.
Additionally, the inspector observed Control Room activities and plant system status at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on October 24, 1978.
The plant areas inspected were as follows:
- Auxiliary Building, Intermediate Building, Turbine Building, Reactor Containment, Safeguard Pump Area, Main and Auxiliary Feedwater Pump Areas, and Cable Tunnel.
(1)
The following observations/determinations were made:
Radiation controls established by the licensee, in-cluding posting of radiation areas, radiation work permits i'n 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 and containment were measured and compared to posted values.
Control Room and local monitors were observed to verify plant operation in conformance with Technical Specification LCO requirements.
Items examined in-cluded:
refueling water storage tank level and boron concentration; accumulator pressure, level, and boron concentration; -spray additive tank volume and sodium hydroxide concentration; boric acide storage tank level, boric" acid concentration, and temperature; condensate storage tank level; nuclear instrumenta-tion; diesel generator start controls; control rod position indication and insertion; reactor coolant system operating parameters, including pressure, temperature, power, offset, total flow, and boron concentration; temperature indications for boric acid heat tracing; and diesel fuel oil level 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 vibra-tions.
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 condi-tions.
Overall plant status was discussed with a control operator.
Control room manning was observed on several occasions during the inspection.
The following valves were observed for proper posi-tiohing:
841, 865, 888A, 888B, 858A, 8818, 873A, 881A, 382, 827A, 827B, 715, 717, 712B, 714, 4791, 4791A, 4795 and 4795A.
The installation of shielding adjacent to the fuel transfer tube inside containment was observed and found to be in accordance with the Licensee's response to IEB 78-08, dated August 11, 1978.
The inspector observed the drawing of a primary
'oolant sample and witnessed the performance of several chemical analyses, to verify approved procedures were in use and that personnel performing the analyses were knowledgeable of procedures and equipment used.
(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 the following procedures:
A-l, "Radiation Control Manual," Revision A-5, "Safety Committee, Revision 3'.
A-54.2, "Ginna Station Staff Res'ponsibilities for Five Prevention,"
Revision l.
OSO C-77-8,
"Cleanup Stations,"
dated January 18, 1978.
A-52.2, "Control of Locked Yalve Operation," Revision 16.
A-36, ".Station Holding Rules," Revision 8.
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.
(3)
Except as noted below, the inspector had no further comments in this area.
(a)
General housekeeping conditions in the plant were found to be acceptable with the exception of,the minor discrepancies noted below:
(1)
several lights were either burned out or missing in the containment basement; (2)'ools and other loose items were found in various work areas inside containment.
Additionally, it was noted that large wooden boxes used for storage of RV head 0-ring seals were stored on the containment operating level and were not treated with fire retardant chemicals;
(3)
evidence of leakage was found on valves 892A and 873A; (4)
the spent fuel pool water needed cleanup; (5)
oil was noted on the south side of the spent fuel pool floor; and, (6)
abnormal vibration was noted on piping identi-fied as part of the charging system (but not part of the RCS injection flow path).
These items were identified to the licensee and discussed at the exit interview.
The licensee was familiar with some of the items and Work Orders already had been submitted; the licensee stated that the other items would be followed by additional Work Orders.
The inspector had no further comments on this area.
(b)
During the tour of the auxiliary building, the in-spectors noted that valve 881A (NaOH drain valve)
was not locked in accordance with Ginna Station Administrative procedure A-52.2 but the valve was in the correct position (closed).
This finding appears to be an isolated ease of a discpepancy in the control of locked valves.
However, the inspector discussed the matter with the licensee at the exit interview and, in particular, he discussed the adequacy of the chain/lock application for the specific type of valve used for V881A.
The licensee stated that this area would be reviewed to assure compliance with A-52.2.
This item is unresolved pending further review of locked valve control by NRC:RI during subsequent inspections (50-244/78-21-OZ).
4.
S lice Insulation The inspector reviewed the newly installed insulation on penetra-tion splices for pressurizer channels LT-426, PT-429, PT-449, PT-430, LT-427, PT-431 and LT-428.
The splices for these circuits were reworked after discrepancies were noted in the original in-stallation of environmentally qualified heat shrink sleeves
(reference:
NRC Region I Inspection Report 50-22/78-20).
All splices reviewed during this inspection, were found to be in con-formance with the applicable requirements.
The inspector also reviewed the plant system circuits which occupied a peripheral pin location in the penetration and which were used in place of the original pins for the pressurizer ci rcuits.
The affected channels were:
PT-174, 'B'CP 81 Seal D/P and FT-178, 'B'CP Leakage High Range for penetration AE-10; NI junction box RTDs for penetration CE-5; FT-175,.'O'CP low Range leakage and NIs junction box RTDs for penetration CE-6.
Circuits were not relocated on penetration AE-ll.
No inadequacies were identified.
The inspector had no further comments on the installation of splice. insulation and unresolved item 244/78-20-01 is considered resolved.
The inspector stated at the exit interview that the following items in the area of environmental qualification of safety related circuits are still open and.subject to NRC review:
submittal of the final evaluation report; completion and review of the qualification tests; completion of the IEC 78-08 review; and review of Rome Cable qualification documentation.
The licensee acknowledged the inspector's comments.
Personnel Chan es The inspector reviewed personnel records for staff changes made in the positi'ons of Plant Superintendent, Assistant Plant Superin-tendent, Maintenance Engineer, Technical Engineer, guality Control Engineer and Nuclear Engineer, as documented in.the licensee's letter to the NRC dated August 2, 1978.
Except as noted below, no problems were identified in meeting the requirements of ANSI N18;l.
The inspector noted that the individual designated for the Nuclear Engi'neer position lacks the required two years experience in Nuclear Engineering.
The licensee acknowledged this information and stated that the August 2, 1978 letter was intended to state that the Technical Engineer (who was the former Nuclear Engineer and meets the ANSI N18.1 requirements)
would fulfillthe responsibilities of the'Nuclear Engineer until the present individual obtains the required experience.-
The inspector had no further questions on this item in light of the above explanation but stated that this matter would be unresolved pending submittal of a change to the Technical Specifications by the licensee (244/78-21-03).
I
6.
NRC Re ion I Review of Event Re orts LERs The inspector reviewed LER's*received in the NRC: I office to verify that details of the event. were clearly reported including the accuracy of the description of cause and adequacy of corrective action, and'he inspector determined whether further information was required from the licensee, whether generic implications were in-volved, andwhether the event warranted on site followup.
The following LER's were reviewed:
LER 78-06, Main Steam Line Snubbers MS146T/8 7..
LER 78-08, Violation of Auxiliary Building Integrity No items of noncompliance were identified.
Onsite Followu of Licensee Events For those LER's selected for on site followup, (denoted by an *
in paragraph 6), the inspector verified that reporting requir'e-ments of Technical Specification had been met, that appropriate corrective action had been taken, that the event was reviewed by the licensee as required by administrative procedures, and that continued operation of the facility was conducted in accordance with Technical Specification. limits.
References:
CARs 1198; 1192 EHR 2190 Meeting minutes for PORC 55-78, 64-78 Procedure M-40.1, Hydraulic Snubber Removal and Installation Procedure, Rev. 4, completed July 7, 1978 and July.10, 1978 Task Assignment SMS 78-09 r
RF-52, Inspection Procedure for Exxon Nuclear Fuel Assemblies at R.
E. Ginna, Rev.
1, August 30, 1978 RF-8, Fuel Assembly and Core Components Movement Prerequisites and Precautions, Rev. 8, April 1, 1978
-I
G S-34, Vital Access Control, Rev. 4, September ll, 1978 Work Order and Trouble Reports TC 78-2043, TC 78-2044 A-17, PORC Operating Procedure, Rev.
A-25, Reporting Unusual Plant Conditions, Rev.
A-25.1, Ginna Station Event Report, Rev.
No items of noncompliance were identified.
8.
Followu on Bulletins and Circulars a.
Licensee followup actions regarding IE Bulletins and Circulars were reviewed.
The inspector reviewed facility records, interviewed licensee personnel and observed facility equipment/com-ponents to verify that:
licensee management forwarded -copies of the bulletins/
circulars to appropriate onsite personnel, information discussed in the licensee s bulletin re-sponses was accurate; corrective action was taken as described in the reply; and, the information was reviewed by the licensee in accord-ance with administrative procedures.
b.
The following bulletins and circulars were reviewed:
IEC 78-02, Proper Lubricating Oil for Terry Turbines IEC 78-04, Installation Error that could Prevent Closing of Fire Doors IEC 78-05, Inadvertant SI during Cooldown IEC 78-06, Potential Common Mode Cooling of ECCS Equipment Rooms IEC 78-07, Damaged Components on a Bergen-Patterson Series 25000 Hydraulic Test Stand
IEC 78-09, Arcing of GE NEMA Size 2 Contactors IEC 78-13, Inoperable Service Water Pumps IEC 78-15, Tilting Check Valves Fail to Close with Gravi ty IEC 78-16, Limitorque Valve Actuators IEB 78-06, Defective Cutler Hammer. Type H Relays IEB 78-10, Bergen Patterson Hydraulic Shock Suppressor Accumulator Spring Coils No items of noncompliance were identified.
9.
Review of Periodic and S ecial Re orts a.
Upon receipt, periodic and special reports submitted by the licensee pursuant to Technical Specifications 6.9.1 and 6.9.2 were reviewed by the inspector.
This review included the following considerations:
the report includes information required to be reported by NRC requirements; test results and/or reported information are consistent with'esign predictions and performance specifications and the information reported is supported by facility recordsi planned corrective action is adequate for resolution of identified problems; and, determination whether any information in the report should be classified as an abnormal occurrence.
b.
The following materials were used to conduct this review:
licensee letters to NRR dated August 2, 1978 Reload Safety Evaluation Report, R,
E. Ginna Nuclear Plant, Unit 1, Cycle 7, February, 1977 PT 34.0, Startup Test Program, Rev.
1, completed June 5,
1978
-
PT 34.1, Initial Criticality and A11-Rods-Out Boron Concentration, Rev.
0, completed May 2, 1978 PT 34.2, Moderator Temperature Coefficient, Rev. 0, completed May 2, 1978 PT 34.3, RCC Bank Worth Measurement, Rev. 0, completed May 2, 1978 PT 34.4, RCC Bank D and C Boron Concentration, Rev.
0, completed May 2, 1978 c ~
PT 34.6, At Power Physics Testing, Rev. 0, completed
. May 31, 1978 Within the scope of the above, the following reports were reviewed by the inspector:
Monthly Operating Reports - June through September, 1978 Annual Operating Report - 1977 R.
E. Ginna Nuclear Power Plant, Unit No. 1, Results of Physics Testing, Cycle VII, 1978 No items of noncompliance were identified.
10.
Unresolved Items Unresolved items are those items for which more'in'formation is required to determine whether the items are acceptable or items of, noncompliance.
Unresolved items are contained in paragraphs 3 and S of this report.
ll. *Exit Interview A management meeting was held with licensee representatives (de-noted in.paragraph 1) at the conclusion of the inspection on October 23,.1978.
The purpose, scope and findings of the inspec-tion were discussed as they appear in the details of this. repor ~ --