IR 05000295/1979027
| ML19296B245 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 01/10/1980 |
| From: | Kohler J, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19296B238 | List: |
| References | |
| 50-295-79-27, 50-304-79-26, NUDOCS 8002200317 | |
| Download: ML19296B245 (11) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-295/79-27 and 50-304/79-26 Docket No. 50-295; 50-304 License No. DPR-39, DPR-48 Licensee:
Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690 Facility Name:
Zion Nuclear Power Station, Units 1 & 2 Inspection At:
Zion Site, Zion, IL R.W
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///of?O A-Inspector: Joel E.
hler WW <
cW r D Approved By:
R. L. Spessard, Chief
/hohc Reactor Projects, Section 1 Inspection Summary Inspection on November 6 - December 21, 1979 (Report No. 50-295/79-27, 50-304/79-26)
Areas Inspected: Routine resident inspection of plant operations, maintenance radiation protection, IE Bulletins and Circulars, licensed operator requalification training, rad waste system operation, design changes and modifications, surveillance testing on Unit I and 2, se-curity and non-routine events. The inspection involved 156 inspector hours onsite by one NRC inspector.
Results: Of the areas inspected, no items of noncompliance were identified.
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DETAILS 1.
Persons Contacted
- N. Wancke, Plant Superintendent
- C. Schumann, Operating Assistant Superintendent
- L. Soth, Administrative and Support Assistant Superintendent E. Murach, Maintenance Assistant Superintendent E. Fuerst, Unit 1 Operating Engineer R. Ward, Unit 2 Operating Engineer J. Marianyi, Technical Staff Supervisor J. Gilmore, Assistant Technical Staff Supervisor F. Lentine, Technical Staff Engineer T. Parker, Assistant Technical Staff Supervisor T. Rieck, Technical Staff Engineer P. LeBlonde, Station Nuclear Engineer A. Krawczak, Technical Staff Engineer K. Ainger, Technical Staff Engineer T. 011ing, Engineering Assistant B. Meyer, Health Physicist F. Ost, Health Physicist F. Reseck, Station Health Physicist J. Wennerholm, Engineering Assistant K. Depperschmidt, Modification Coordinator R. Turner, Shift Foreman M. Romano, Nuclear Station Operator G. Rowe, Nuc' ear Station Operator G. Keene, Nuclear Station Operator S. Ban, Training Instructor C. Schultz, Training Supervisor
- R. Rostkowski, Quality Assurance Engineer 2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (295/79-24-04):
Diesel Generator Roller Pin Inspection.
Zion Generating Station performed an inspection of the roller pin assembly in all diesel generators.
No abnormal wear of the roller pin assembly was found. The inspection was done with the assistance of the Cooper Besemer Company.
No items of noncompliance were identified.
3.
Monthly Operating Summary Unit 1 The unit remained in cold shutdown the entire reporting period for repair of feedwater piping system cracks, and low pressure turbine cracks.
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Unit 2 The unit remained in cold shutdown the entire reporting period for repair of feedwater piping system cracks.
4.
Maintenance Station maintenance activities of safety related systems and com-ponents were reviewed to ascertain that they are conducted in ac-cordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specification requirements.
The following items were considered during this review:
the limiting conditions for operations were met while components or systems were removed from service; approvals were obtained prior to initiating the work; maintenance activities were accomplished using approved procedures; maintenance activities were inspected as applicable; functional testing and/or calibrations were performed prior to re-turning components or systems to an operating status; quality con-trol records were maintained for maintenance activities; and maint-enance activities were accomplished by qualified personnel.
The inspector observed maintenance in progress concerning the following work requests:
03490 Steam Generator Snubber ID, 03489 Stean Generator Snubber IB, and 03559 Steam Generator Snubber IC.
The inspector reviewed the following completed work packages:
01745 SVAG Valve Rewire, 01744 SVAG Valve Rewire, and 01743 rewire control room switches.
No items of noncompliance were identified.
5.
Plant Operations The inspector reviewed the plant operations including examinations of control room log books, routine patrol sheets, shift engineer log book, equipment outage logs, special operating orders, and jumper and tagout logs for the month of November and December,1979. The inspector observed plant operations during several offshifts during the months of November and December, 1979.
The inspector also made visual observations of the routine surveillance and functional tests in progress during the period. This review was conducted to verify that facility operations were in conformance with the requirements established under Technical Specifications, 10 CFR, and Administra-tive Procedures. A review of the licensee's deviation reports for the period was conducted to verify that no violations of the licen-see's Technical Specifications were made. The inspector conducted a tour of Units 1, 2 containment, auxiliary and turbine buildings throughout the period and noted that the monitoring instrumentation-3-
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was recorded as requited iiation controls were properly estab-lished, fluid leaks and ye vibrations were minimal, seismic re-straint oil levels appeared
'. equate, equipment caution and hold cards agreed with control room records, plant housekeeping condi-tions/ cleanliness wa-adequate, and fire hazards were minimal.
The inspector obst t..hift turnovers to verify that plant and component status and problem areas were being turned over to re-lieving shift personnel.
No items of noncompliance were identified.
6.
Physical Protection - Security Organization The inspector verified by observation that at least one full time member of the security organization who has the authority to direct the physical security activities of the security organization was onsite at all times; verified by observation that the security organization was properly manned and verified by observation that members of the security organization vare capable of performing their assigned tasks. There were no weapons qualifications con-ducted during this monthly inspection.
No items of noncompliance were identified.
7.
Physical Protection - Physical Barriers The inspector verified that certain aspects of the physical bar-riers and isolation zones conformed to regulatory requirements and commitments in the physical security plan (PSP); that gates in the protected area were closed and locked if not attended; that doors in vital area barriers were closed and locked if not attended; and that isolation zones were free of visual obstructions and objects that could aid an intruder in penetrating the protected area.
No items of noncompliance were identified.
8.
Physical Protection - Access Control (Identification, Authorization, Badging, Search, and Escorting)
The inspector verified that persons and packages were identified and authroization checked prior to entry into the protected area (PA), vehicles were aroperly authorized prior to entry into a PA, persons authroized in the PA were issued and displayed identifica-tion badges, records of access authorized conformed to the PSP, and personnel in vital areas were authorized access; verified that persons, packages, and vehicles were searched in accordance to re-gulatory requirements, the PSP, and security procedures; verified that persons authorized escorted access were accompanied by an escort when within a PA or vital area; verified that vehicles authorized-4-
escorted access were accompanied by an escort when within the PA; and verified that the escort observed above was authroized to per-form the escort function.
No items of noncompliance were identified.
9.
Physical Protection Communications The inspector verified by observation that communications checks were conducted satisfactorily at the beginning of and at other prescribed time (s) during the security personnel work shift and that fixed and roving posts, and members of the response team successfully communicated from their remote location.
No items of noncompliance were identified.
10.
Review and Followup on Licensee Event Reports Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Speci-fications.
Unit 1 Unit 2 79-90 79-74 79-53 79-87 79-73 79-52 79-85 79-72
,9-51 79-84 79-71 79-49 79-83 79-70 79-82 79-69 79-81 79-68 79-79 79-66 79-78 79-76 No items of noncompliance were identified.
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11.
Surveillance of Safety Related Systems / Components Required by Technical Specifications The inspector observed or audited Techncial Specifications required surveillance testing (other than calibrations and checks) on the followi lg:
(1) Unit 1 ECCS full flow test (2) PT-2C SI-RHR valve interlocks (3) PT-2A SI pump tests (4) PT-3C Penetration Pressurization System (5)
PT-3A Accumulated Boron Sample (6) PT-10A Safeguards Actuation (7) PT-2 D.G. Surveillance The inspector verified that these tests were performed in accordance with technically adequate procedures, that these results were in con-formance with Technical Specifications and procedure requirements and were reviewed by perscnnel other than the individual directing the test, and that any deficiencies identified during testing were
, properly reviewed and resolved by appropriate management personnel.
No items of noncompliance were identified.
12.
IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presentation in the bulletin and the licensee's response, that licensee managment forwarded cop-ies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's writ-ten response was accurate, and that corrective action taken by the licensee was as described in the written response.
IEB 79-23 IEB 79-24 These bulletins are closed out.
No items of noncompliance were identified.
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13.
Radioactive Waste Systems - Operations
.
The inspector verified through record review that several effluent releases which occurred during the month of November, 1979 were properly documented, that timely approvals of the releases were obtained, and that required sampling had been accomplished.
No items of noncompliance were identified.
14.
Licensed Operator Requalification Training The inspector audited the licensee's operator requalification lecture series and verified adequacy of the technical content of presented information.
No items of noncompliance were identified.
15.
Radiation Protecticn - Operations The inspector examined several radiation protection instruments in use and verified operability and currency of calibration, ex-amined several SWP's and verified operations conducted under the SWP's were in accordance with licensee procedures and verified that high radiation area posting was acceptable inside Unit 1 and Unit 2 containment.
No items of noncompliance were identified.
16.
Emergency Operating Procedure Review The inspector reviewed Diagnostic Procedure Revision E0P-0 and Small Break LOCA Procedure Revision E0P-9 to determine that Westinghouse Owners' Group recommendations were made part of the Zion Procedures.
In addition, the inspector questioned several control room operators in order to determine the adequacy of the small break LOCA procedure.
From review of the procedure and discussion with control room operators it was determined that for the maximum break, recircu-lation switchover may have to begin before the Lo Lo RWST alarm occurs, in order that flow interruption does not occur.
The ac-ceptability of an early recirculation switch over under maximum break conditions is presently being discussed with NRR.
Conse-quently, the final review of E0P-9 and E0P-0 will be done after the NRR review.
The emergency operating procedure review is designated an unresolved item (295/79-27-01; 304/79-26-01).
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'7.
Gouged Bergen-Paterson Steam Generator Snubbers
.
ucring routine surveillance in the Unit I containment three Bergen-Pater _an (B-P) hydraulic shock suppressors (snubbers) installed on the steam generators were found to be leaking fluid. The shock suppressors were removed fro,m the steam generators for inspection.
The snubbers were torn down in the maintenance shop. The inspector witnessed the tear down and observed along with the licensee that significant gouging had occurred in the gland area and on the ram.
The resident inspector notified the Region III snubber specialist of the gouging.
A special snubber inspection was made by the RIII specialist to look at the affected snubbers and discuss possible corrective action.
Through joint discussions with Region III, IE-HQ and the Zion Generating Station, a special operability test was proposed to determine whether the snubbers, could perform their safety func-tion in a condition that may be gouged.
The licensee is perform-ing this test with the assistance of Wyle Laboratory, Huntsville, Alabama.
At this point in time, no test results are available. The adequacy of the Bergen-Paterson snubbers is classified as an unresolved item and will be reviewed further in the near future (295/79-27-02; 304/79-26-02).
No items of noncompliance were identified.
18.
Cracks In Unit 1 Low Pressure Turbine During turbine overhaul and inspection, the licensee discovered two cracks, each approximately one inch deep and one inch in length on low pressure turbine stage number 3, disc number 1, governor end.
The cracks were discovered using a Westinghouse developed procedure envolving ultra sonic single transducer equipment. The inspection was performed using the radial aim technique while the length and depth were determined by a tangential technique.
The cracks are not in the keyways.
Westinghouse and Zion Generating Station concluded that the affect-ed rotor must be removed and the blading on the symmetric disc cut-off.
Baffles will be installed in the stationary blade section to make-up the required pressure drop.
The inspector observed the removal of the disc and blading.
Upon removal, samples were sent to the Commonwealth Edison Operational Analysis Laboratory for inspection to determine the cause.
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The information contained here was passed on to IE for review.
- Westinghouse addressed generic turbine keyway cracking in an NRR meeting on December 17, 1979.
This item is closed.
No items of noncompliance were identified.
19.
Discovery of Inadequate Westinghouse Generic Rod Drop Accident As a result of an ongoing review by Westinghouse, additional con-cerns relative to rod drop events were analysed. Application of single failure criteria to the rod control system developed possible scenarios whereby multiple rod drop events could occur without the reactor tripping. The result could possibly lead to a nonconserva-tive DNBR condition.
A meeting was held in Bethesda, MD on November 19, 1979 between affected utilities, Westinghouse, and NRR. As a result of this meeting, an interim solution was agreed upon to prevent possible scenarios that could lead to nonconservative DNBR conditions dur-ing hypothetical multiple rod drop accidents. The solution is as follows:
1.
Less than 90% power, no additional requirements on rod control system.
2.
Greater than 90% power control bank D must be greater than 215 steps withdrawn whenever the rod control system is in automatic.
Zion committed to these two requirements. This item will be reviewed when the units return to power and is designated an unresolved item (295/79-27-03; 304/79-26-03).
21. Design Changes and Modifications The inspector reviewed for completeness three modification packages performed on Unit 1 and 2 during the current outage. The modifica-tion packages involved:
(1) rewire of the previously de-energized SVAG valves so that direct verification of positive indication could be ascertained; (2)
replacement of MSIV relays with new GE DC sealing relays.
The review involved determination that the following requirements had been met:
1.
traveler signed-9-
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2.
10 CFR 50.59 review complete
,
3.
work request completed 4.
functional test satisfactory S.
quality assurance review 6.
work procedures signed 7.
part tickets and certifications enclosed The inspector observed portions of the functional test of these two modifications.
No items of noncompliance were identified.
22.
IE Circular Follouup For the IE Circular listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and that if the circular were applicable to the facility, appropriate corrective actions were taken or were scheduled to be taken.
IEC 79-17 This Circular is closed out.
No items of noncompliance were identified.
23.
Meetings Attended During November and December, 1979 November 27, 1979 - Emergency Operating Procedure Training - Glen Ellyn, IL.
December 5, 1979 - Emergency Planning Meeting - Bethesda, MD.
December 20, 1979 - Emergency Planning Meeting - Bethesda, MD.
24.
Unresolved Items Unresolved items are matters which more information is required in order to ascertain whether they are acceptable items, items of non-compliance or deviations.
Unresolved items disclosed during the inspection are contained in paragraphs 19, 17 and 16.
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25.
Exit Interview
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The inspector met with licensee representatives (denoted in Para-graph 1) throughout the month and at the conclusion of the inspec-tion December 21, 1979 and sununarized the scope and findings of the inspection activities. The licensee r.cknowledged the inspector's comments.
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