ML20032E798

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{{#if:ML20032E798|Download: [[URL::http://pbadupws.nrc.gov/docs/{{#sub:ML20032E798%7C0%7C6}}/ML20032E798.pdf%7CML20032E798]]|[[URL::http://pbadupws.nrc.gov/docs/{{#sub:%7C0%7C6}}/.pdf%7C]]}} {{#if:8|(page count::8)}}
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}}{{#if:INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS|{{#arraymap:INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS|,|x|| }}{{#if:{{#show:ML20032E798|?site}}|{{#invoke:Navbox|navbox}}

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|{{#if:ML20032E798|Download: [[URL::http://pbadupws.nrc.gov/docs/{{#sub:ML20032E798%7C0%7C6}}/ML20032E798.pdf%7CML20032E798]]|[[URL::http://pbadupws.nrc.gov/docs/{{#sub:%7C0%7C6}}/.pdf%7C]]}} }} See also: see also::IR 05000267/1981020

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{{#Wiki_filter:.- . = _ - . . - . - - - . ' - < APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV IE Inspection Report: 50-267/81-20 License DPR-34 i Docket: 50-267 Licensee: Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201 i Facility Name: Fort St. Vrain Nuclear Generation Station Inspection at: Fort St. Vrain Site, Platteville, Colorado , Inspection Conducted: September. 1-30, 1981 1 - Inspectors: dd(I6 M /8- W l M. W. Dickerson, Senior Resident Reactor Inspector Date ' %W /6- 3 f?-9 I

G. L. Plumlee III, Resident Reacttr Inspector Date

Approved by: ~

  1. ~3# W

T. F. Vesterman, Chief, Reactor Project Section 1 Date Inspection Summary Inspection conducted September 1-30, 1981 (Report: 50-267/81-20) Areas Inspected: Routine, announced inspection of Surveillance; Maintenance; , Operational Safety Verification; Plant Operations; Review of Periodic and Special Reports; and IE Bulletins. The inspection involved 271 inspection- hours on site by two NRC inspectors. l i Results: Within the six areas inspected, three violations were identified (Failure to adhere to Technical Specifications, paragraph 2; failure to 4 follow procedures, paragraph 4; and failure to meet the requirements of 10 CFR Part 2.201, paragraph 7). 1 t 1 1 i 8111230278 811106 PDR ADOCK 05000267 ' G PDR . .__ _ , _ . _ . _ . , _ . . _ . , . _ _ _ . _ _ . . _ . _ . . _ . . _ . . _ . . . _ . _ . . . . _ . _ - - . . _ _ . _ _ . _ - . . _ , . . . , _

. 2 DETAILS 1. Persons Contacted T. Borst, Radiation Protection Manager M. Block, Superintendent of Operations R. Craun, Acting Site Engineering Coordinator D. Evans, Shift Supervisor M. Ferris, Technical Services Engineer W. Franek, Results Supervisor J. Gahm, QA Manager E. Hill, Operation Manager W. Hillyard, Administrative Services Manager D. Hood, Shift Supervisor J. Liebelt, Senior Maintenance Supervisor M. McBride, Technical Services Manager J. Reese, Supervisor Nuclear Engineering Department L. Singleton, Superintendent Operation QA J. Van Dyke, Shift Supervisor D. Warembourg, Manager Nuclear Production R. Webb, Maintenance Supervisor V. Wetzbarger, SCH/ Stores /QC Supervisor The NRC inspector also contacted other plant personnel including reactor operators, maintenance men, electricians, technicians and administrative personnel. 2. Operational Safety Verification The NRC inspector reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements, and the licensee's management control system is effectively discharging its responsibiiities for continued safe operation. The review was conducted by direct observation of activities, tours of the facility, interviews and discussion with licensee personnel, independent verification of safety system status and limiting condition for operations, and review of facility records. Included in the inspection were observation of control room activities, review of operational logs, records, and tours of accessible areas. Logs and records reviewed included: Shift Supervisor Logs . Reactor Operator Logs .

- . 3 Equipment Operator Logs . Auxiliary Operator Logs . Technical Specification Compliance Logs . Operations Order Book . System Status Log . Form 1 Log (Jumper Log) . Plant Trouble Reports . During tours of accessible areas, particular attention was directed to the following: Monitoring Instrumentation . Radiation Controls . Housekeeping . Fluid Leaks . Piping Vibrations . Hanger / Seismic Restraints . Clearance Tags . Fire Hazards . Control Room Manning . Annunciators . The operability of selected systems or portians of systems were verified by walkdown of the accessible portions. The NRC inspector verified the operability of the Purification Cooling Water System. Procedures were also reviewed and implementation observed for Gaseous Effluent Releases No. 566, No. 568, No. 569, and Liquid Waste Release No. 494. The releases appeared to have been made in a satisfactory manner. l - _ _ ______ _ -_ - _ _ - ___- _ -___ _ _ _ - _ -_____ _ _____--_ - ______ - __ -_. - .__ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

- . - - ._ -. - . . 4 Control Room Observation During observations in the Control Room on September 23, 1981, at 10:00 a.m. (MDT), it was determined by the NRC inspector that Loop Moisture Monitors MM1117 for Loog 1 and MM1121 for Loop 2 were not at the setting for a dewpoint of 22 F as required by the Master Setpoint List. The Master , SetpointListrequfreseachof-thesetobeatasettingof3.09whichis equivalent to a 22 F dewpoint. The Technical Sepcification LC0 4.4.1,- " Plant Protective System Instrumentation," Table 4.4-1, Item 4, ' Primary Coolagt Moisture, Loop Monitor," specifies an absolute low trip setting

of 27 F dewpoint. ' TheobservedsettingswerethatMM1117wasat5.g9andthatMM1121was

at 3.29. A5.09sei.tingisequjvalenttoa92.5Fdewpointanda3.29 setting is equivalerit to a 29.3 F dewpoint. Each of these settings is in the nonconservative direction and each was checked to confirm that they were not tripped as permitted by the Technical Specifications. The as-found settings effectively reduced the Loop 1 trip logic to a situation where it would require the trip of the other two Loop 1 Low Set Moisture Monitors, plus one high set moisture monitor in either loop to initiate a scram. ThiscombinationwouldberequiredsinceMMf117was set above the High Set Moisture Monitor dewpoint trip point of 62 F. Loop 2 would operate as it is designed except that the two out of three logic for the Low Set Moisture Mogitors would not be effective until the dewpcint reached approximately 29 F. Howevgr,theothertwoLowSet Monitors would already have tripped at a 22 F dewpoint. 3 2 A review of the Operator's Data Log #1 for the readings taken on the 12:00 p.m. - 8:00 a.m. shift, September 23, 1981, indicated that the moisture monitors were set at the required 3.09. Discussions with the , ' on-duty operators and shift supervisor did not reveal any reason for the setting discrepancies. The above matter was discussed with a representative of the licensee

who was informed that failure of the moisture monitor to be at the j required settings was considered a violation.

The inspector had no adM tional questions ir. this area. 3. Surveillance (Monthly) The NRC inspector reviewed all aspects of surveillance testing involving . safety-related systems. The review included observation and review , relative to Technical Specification requirements. The surveillance tests reviewed and observed were: ' SR 5.4.1.1.10.b-M, Circulator Inlet Temperature Scram Test

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SR 5.4.1.1.13.a-M, Two Loop Trouble Scram Test SR 5.6.2a-W, Station Battery and PPS Check

I

- . 5 SR 5.2.10.a.4-W, Diesel Driven Fire Pump Battery and Charger Weekly Inspection SR L.4.1.3.3b-M, Circulator Bearing Water Pressure Test SR 5.4.1.1.14.a-M, Plant 480V Power Loss Scram Test SR 5.8.labc-M, Radioactive Gaseous Effluent System Test SR 5.8.2bc-M, Radioactive Liquid Effluent System Instrumentation Functional Test No violations or deviations were identified. 4. Maintenance (Monthly) The NRC inspector reviewed records and observed work in progress to ascertain that the following mainte m ce activities were being con- ducted in accordante with approved procedures, Technical Specifica- tions, and appropriate Codes and Standards. The following maintenance activities were reviewed and observed: PTR 9-92, K-9206X "D" Diesel Generator Engine Repair in accordance with PM 92.10, " Inspection and Preventive Maintenance Procedures Caterpillar Diesel Engine" PTR 9-51, PS 6339 repair in accordance with RP #177, "Foxboro Model T-630 Transmitter Operation, Maintenance, and Calibration" PTR 9-68, SV-2105 repair in accordance with MP 91-21, " Maintenance and Repair of System 91 Hydraulic Valve Actuators" PTR 9-73, P-8404SX Auxiliary Boiler Fuel Oil Pump repair in accordance with PM 82.1, " Auxiliary Boiler Fuel Oil Pumps P-8404X and P-8404SX Inspection and Preventive Maintenance Procedure" PM 92.1, Preventive Maintenance Inspection on C-9202X, compressor for the diesel start motor PTR 6-54, BFS-30E Hydraulic snubber repair in accordance with MP 98-1, " Repair and/or Testing of Hydraulic Pipe Snubbers" CWP 81-40/CN1096 Replace P-2107 with a new 12 stage closed impeller / bowl shaft assembly in accordance with Operations and Maintenance Manual, "Goulds Pumps Model VIC" PMR-1-M, Buffer /Mid-Buffer Operability Check . - - - - - - - - - - - - - - . - - - - - . - -

- . 6 Class 1 Hydraulic Snubber Repair On September 15, 1981, at 11:00 a.m. (mbt), the NRC inspector initiated an inspection on maintenance activities performed on hydraulic snubber BFS-30E. At this time, the snubber was mounted on the test stand and was being filled in preparation for testing'. A review of the procedure that was used for the repairs to the snubber, MP 98-1 Repair and/or Testing of Hydraulic Pipe Snubbers, indicated that five maintenance cuality control hold points had not been signed. Administrative Services Procedure ASP-3, " Maintenance Quality Control Program," and MP 98-1 both contain the requirement that the hold point is to be signed before work shall be allowed to continue. Two unsigned hold points in steps 4.10.3 and 4.10.4 of MP 98-1 involved setup of the test stand; two unsigned hold points in steps 4.14.3 and 4.15.1 of MP 98-1 involved verification that repairs were performed in accordance with the correct attachments to the procedure for this type snubber; and one unsigned hold point in Attachment B, Step 13 of MP 98-1 involved verification of torque requirements. The NRC inspector discussed the above with the licensee and informed the licensee that failure to follow procedures which are Technical Specification requirements is considered a violation (d120-02). The NRC inspector had no additional questions in this area. 5. Review of Plant Operations The NRC inspector reviewed the procurement and storage aspect of facility operations to determine if it was being accomplished in accordance with regulatory requirements. To accomplish this the NRC inspector selected one safety-related item, a helium dryer P. O.

  1. N-2999A, to verify traceability of the item and records and

inspect the storage location to verify that'the nonconforming item was segregated and marked / tagged appropriately (QA Hold Tag #00169). The NRC inspector also verified that the item was stored in accor- dance with licensee procedures and vendor specifications and con- formed to any preventive maintenance, housekeeping, or environmental requirements while in storage. No violations or deviations were identified. 6. Control of Heavy loads The NRC inspector reviewed the licensee's response to the generic letter, " Control of Heavy Loads," dated December 22, 1980, as a con- tinuing verification to assure the safe handling of heavy loads. Procedural review was documented in IE Inspection Report 50-267/81-16. The review of the licensee's response indicated that: (1) the licensee's response was submitted within nine months versus the requested six

- . 7 months; (2) Item 1, Paragraph 3b, incorrectly references Section 7.4.2 of the Technical Specifications which should be changed to uad Section 7.4 since Section 7.4.2 does not exist; and (3) Item 1, Paragraph 3f, did not include a verification that crane design complies with Chapter 2-1 of ANSI 830.2-1976, or a demonstration of equivalency of actual design requirements for instances where specific compliance with this standard is not provided. The above was discussed with a representative of the licensee and the NRC Project Manager, Fort St. Vrain. The NRC inspector has no further questions in this area. 7. Reporting Requirements A review of the licensee's responses to Notices of Violations indicated that responses to violations inc.luded in IE Inspections 81-11, 81-12 and 81-13 had not been received within the specified time for response. , Specified response times were 25, 30 and 30 days, respectively, for IE Inspection Reports 81-11, 81-12 and 81-13. An initial response to all three notices was received in Region IV on September 28, 1981. 10 CFR, Title 10, Part 2.201(a) requires that responses to Notices of Violation be submitted by the licensee within the specified time. Contrary to this requirement, responses were not received within the specified times. This was discussed with the licensee who was informed that failure to respond within the specified time was considered a violation (8120-03). The licensee has reinstructed the appropriate personnel on the duties and responsibilities related to submitting responses to NRC correspondence. No response to this violation is required. 8. IE Bulletin The NRC inspector verified by record review, observation and discussion with the licensee, the action taken in response to IE Bulletins. The following Bulletin was reviewed: 81-02, Supplement 1, Failure of Gate Valves to Close Against Differential Pressure. The licensee has determined that Westinghouse valves of 6 , 8 , 10 , 12 , 14 , and 18-inch nominal size have not been purchased or installed at Fort St. Vrain (See IE Inspection Report 81-11 regarding 3- and 4-inch valves). No violations or deviations were identified.

.. , 8 9. Report Reviews The NRC inspector reviewed the following reports for content, reporting requirements and adequacy: Monthly Operating Information Report, August 1981 Monthly Operations Report, August 1981 No violations or deviations were identified. 10. Exit Interview Exit interviews were conducted at the end of various segments of this inspection with Mr. D. Warembourg, Manager, Nuclear Production, and/or other members of the Public Service Company staff. At the interviews, the inspector discussed the findings indicated in the previous paragraphs. The licensee acknowledged these findings. , }}

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