ML20050E355
| ML20050E355 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/10/1982 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20050E309 | List: |
| References | |
| 50-267-82-05, 50-267-82-5, NUDOCS 8204130233 | |
| Download: ML20050E355 (11) | |
See also: IR 05000267/1982005
Text
{{#Wiki_filter:- . APPENDIX B U. S. NUCLEAR REGULATORY C0iHISSION REGION IV NRC Inspection Report: 50-267/82-05 License DPR-34 Docket: 50-267 Licensee: Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility Name: Fort St. Vrain Nuclear Generation Station Inspection at: Fort St. Vrain Site, Platteville, Colorado Inspection Conducted: February 1-28, 1982 Inspectors: ) [r [ b 3 - 10- 1 2 M. W. Dickerson, Senior Resident Reactor Inspector Date [ hk 3 -/0 -7 2- G. L. Plumlee III, Resident Reactor Inspector Date Approved By: 7[[ 3 -10-9 L- T. F. Westerman, Chief, Reactor Project Section A Date Inspection Summary Inspection conducted February 1-28, 1982 (Report: 50-267/82-05) Areas Inspected: Routine, announced inspection of Surveillance; Maintenance; Inspection During Long-Term Shutdown; Startup Testing Modified System; Trans- portation Activities; Power Level Plateau Review; Follow Up of Written Reports of Nonroutine Events; Follow Up of Previous Inspection Findings; and Review of Periodic and Special Reports. The inspection involved 170 inspection-hours on site by two NRC inspectors. Results: Within the nine areas inspected, one violation was identified (Failure to adhere to Technical Specification, Paragraph 3).
8204130233 820317 PDR ADOCK 05000267 G PDR ,
I - , 2 DETAIL 1. Persons Contacted M. Block, Superintendent of Operations , ' T. Borst, Radiation Protection Manager
B. Burchfield, Results Engineering Supervisor l M. Deniston, Shift Supervisor W. Franek, Nuclear Site Engineering Manager C. Fuller, Technical Services Engineering Supervisor J. Gahm, QA Manager E. Hill, Operations Manager J. Liebelt, Senior Maintenance Supervisor M. McBride, Technical / Administrative Services Manager j F. Novachek, Technical Advisor G. Reigel, Shift Supervisor ' T. Schlieger, Health Physics Supervisor L. Singleton, Superintendent Operations QA l J. Van Dyke, Shift Supervisor l D. Warembourg, Manager Nuclear Production ! R. Webb, Maintenance Supervisor l W. Woodard, Health Physicist l The NRC inspectors also contacted other plant personnel including reactor operators, maintenance men, electricians, technicians, and administrative personnel. 2. Licensee Action on Previous Inspection Findings (Closed) Open Item (50-267/8105-01) Review Masonry Walls With Attached Safety-Related Electrical Conduit. The licensee completed an evaluation, including load tests of representative attachments on the masonry walls. The evaluation did not disclose any loadings which were outside accept- able limits. (Closed) Violation (50-267/8105-02) Systems Associated With the Sixteen Masonry Walls Found to be Structurally Inadequate were not Described, Analyzed for Operability, and Subsequently Reported to the NRC. All , l 16 walls were reinforced to provide structural adequacy. Additionally, the individual responsible for the bulletin was reinstructed and a provision was included in a revision to Procedure ENG-7 which requires ~ a review of the contents of responses to bulletins to assure all subject matter is addressed. (Closed) Violation (50-267/8118-01) Failure to Log Required Information. All personnel involved and responsible for keeping logs in accordance with Procedure P-1 were required to review the procedure. (Closed) Violation (50-267/8118-04) Failure to Seal V-22184 Main Steam Electromatic Relief Valve Shutoff Valve. Operations personnel were instructed to ensure compliance with the requirements of OPOP III. L --
. - - - . ] 3 ! 3. Inspection During Lonc-Term Shutdown The NRC inspector reviewed licensee activities during an extended shutdown to ascertain that the facility is being maintained in conformance with regulatory requirements and that the licensee's management control system is effectively discharging its responsibilities for continued safe shutdown. The review was conducted by direct obser- a ' vation of activities, tours of the facility, and discussions with licensee personnel. Included in the inspection were observation of control room activities, review of ooerational logs, records, and tours of accessible areas. ' Logs and records reviewed included: Shift Supervisor Logs . Reactor Doerator Logs . Equipment Operator Logs . 1 Auxiliary Operator Logs . Technical Specification Compliance Logs . Operations Order Book . ) Operations Deviations Reports . Clearance Log . Temporary Configuration Reports . Plant Trouble Reports . 1 During tours of accessible areas, particular attention was directed to the followino: Monitorino Instrumentation . Radiation Protection Controls . Housekeeping . Physical Security Implementation . Plant / Equipment Conditions . Activities in Progress . Clearance Taas . ! Fire Hazards . ' Control Room Mcnnino . i ! . - . - - .
. . 4 Annunciators . The inspection also consisted of: a. Review of the licensee's Jumper / Bypass controls (Temporary Configuration Report Log and the System Abnormalities Clearance Log) to verify that there are no conflicts with Technical Speci- fications, the licensee is actively pursuing correction to conditions requiring jumpers, and jumper / bypasses have been installed and removed properly, b. Independent verification of Clearance Number 3193 to verify that a tagout system is in effect and that tagouts are properly conducted. c. Witnessing portions of the functional test, FT-1110-2, for the Buffer Mid-Buffer switch installation in accordance with CN 1110/ CWP 81-54-1 prior to the return of the switches to service to verify the adequacy of the licensee's work. d. Verification that surveillance tests required during the shutdown were being performed. e. Verification that the licensee's problem identification system (trouble reports) was functioning. , f. Verification of the implementation of racioactive waste system controls by witnessing Liquid Waste Release No. 519 and. Gaseous Waste Release No. 586. During a review of the Shift Supervisor's Log on February 2,1982, at 6:30 a.m. MST, the NRC inspector determined that the licensee had reported a Significant Event in accordance with 10 CFR 50.72(a)(8), as a result of an inadvertant radioactive liquid waste release to the environment. This immediate notification was followed by Report- able Occur [ence Report No. 50-267/82-004, dated February 16, 1982. The inadvertent release occurred during the transfer of the contents of lA Receiver (T-6202) to the Monitor Tank (T-6204) when on February 2, 1982, at 12:45 a.m. MST, a valve (V-6297) was discovered open which allowed approximately 250 gallons of radioactive liquid waste to be discharged to the environment. Upon a review of the possible causes, the NRC inspector determined that prior to the event a surveillance SR 5.8.2bc-M for Liquid Waste Release No. 518 had been completed on February 1,1982, at 11:15 p.m. MST which required V-6297 to be returned to its normally closed position. The NRC inspector also determined that the procedure S0P 62, Revision 23 dated September 21, 1981, used to transfer the contents of the Receiver to the Monitor Tank also required checking V-6297 closed prior to the start of the
. . 5 Liquid Waste Transfer Pumps. Water sample analysis indicated that the concentration of radionuclides in the cooling tower blowdown water discharge did not exceed the values specified in Table II, Column 2,10 CFR 20, Appendix B, for unrestricted areas. However, the sample taken from the 1A receiver tank indicated a beta-aamma level in excess of that oermissible by LC0 4.8.2 for gross beta-gamma . activity prior to release to the environment. ' The licensee was informed by the NRC inspector that failure to follow procedures which are Technical Soecification reauirements and failure to comply with a Limiting Condition for Goeration is considered a violation (8205-01) The NRC inspector had no further questions in this area. 4. Surveillance (Monthly) The NRC inspector reviewed all aspects of surveillance testina involving safety-related systems. The review included observation and review relative to Technical Soecification requirements. The surveillance tests reviewed and observed were: SR 5.8.2bc-M Radioactive Liquid Effluent System Instrumentation Functional Test (Release No. 519) SR 5.8.labc-M Radioactive Gaseous Effluent System Test (Releases No. 586 and 587) SR 5.8.lcd-0 Radioactive Gaseous Effluent System Calibration SR 5.6.2c-A Station and PPS Batteries Check SR 5.3.8a-X Hydraulic Snubbers No violations or deviations were identified. 5. Maintenance (Monthly) The NRC inspector reviewed records and observed work in orogress to ascertain that the following maintenance activities were beina conducted in accordance with approved orocedures, Technical Soecifications, and appropriate Codes and Standards. The following maintenance activities were reviewed and observed: CN 1307A/CWP 82-21 Modify FSV Computer System CN 1433/CWP 82-27 Install Added Control in 62 System HSV/HV-62249 PTR 2-366 Repair HRS 381 in accordance with MP 98-1, " Repair and/or Testina of Hydraulic Pine Snubbers" .
. 6 PTR 11-149 Hydraulic Accumulator Loop 2 11-150 Groups 1 thru 2 'O' Ring 11-151 Replacement in accordance with 11-152 MP 91-24, " Maintenance and Repair of System 91 Hydraulic Accumlators" No violations or deviations were identified. 6. Transportation Activities The NRC inspector reviewed the shipment of PGX Graphite samples to verify compliance with NRC and certain DOT regulatory requirements. The shipment was classified Normal Form Type A; Transportation Groups III and IV; Transport Index 0.2; and shipped in a Type A drum. The NRC inspector verified from licensee documentation and observation that: a. The licensee had made a determination that the new package (originally a Type 17C five-gallon metal drum) had been tested by Monsanto Research Corporation in accordance with MLM-2228, 1975, and did meet the Type 7A design requirements of the D0T specifications for shipment of Type A material. b. The package does conform with the approval criteria and has met the minimum outside dimension requirement. c. The licensee, in accordance with written procedures, maintains on file and is prepared to provide a copy of the certification (MLM-2228,1975) and supporting safety analysis demonstrating that the construction methods, package design, and materials of construction are in compliance with the specification. d. Prior to first use, the licensee assured that the package met the specified quantity of design and construction and verified the effectiveness of the shielding and containment. e. The licensee assured that the outside package incorporated a security seal and that internal bracing materials were in their proper place. f. The licensee, in accordance with written procedures, assured that the package was properly marked to conform with the requirements for Type A shipments as required by D0T specifications. g. The licensee, in accordance with written procedures, labeled the package as appropriate based on the surface and 3-foot dose-rate limits and other regulatory criteria. _
. . 7 h. The licensee, in accordance with written procedures, assured that the package complied with the radiation level limits at the surface of the package and at 3 feet (transportation index), and that such limits were used to determine the appro- priate package label to be applied. i. The licensee, in accordance with written procedures, had prepared the appropriate shipping paper documentation containing the required information. The NRC inspector identified the following problems which were corrected by the licensee prior to shipment of the Type A material. The package markings were not permanent as required by . 49 CFR 173.24(c)(1)(iii). A safety analysis had not been performed by the licensee as . required by 49 CFR 173.395(a)(1). The package was not marked with the name and address of the . consignee or consignor as required by 49 CFR 172.306. There was nothing in the shipping documentation to ensure that . the minimum separation requirements of 49 CFR 177.842(b) were met. No violations or deviations were identified. 7. Startup Testing - New or Modified Systems The NRC inspector is reviewing the licensee's Startup Testing Program associated with the installation of a modified system (System 21 Modification Program) to ascertain whether the program conformed with Regulatory requirements, licensee approved procedures, and administra- tive controls. As of this reporting period, the NRC inspector has verified by reviewing and witnessing portions of the licensee's test (T-191) to verify proper operation of the Helium Circulator Auxiliary System that the testing of this modified system important to safety was conducted in accordance with approved procedures and manufacturer's recommendations. No violations or deviations were identified. 8. Power Ascension Program a. Scope of Inspection The inspector reviewed selected test data associated with the power ascension program. Specifically reviewed was the test data developed at 100% power level.
Q . . 8 Included in the reviews were the licensee's evaluation of the data, test changes, test deficiencies, data sheets, QA audits, and test data approval. Reviewed were Technical Review Committee Meeting Minutes and the records of a QA Audit conducted in accordance with QAAM PI-19. Included in the review were test T-164 which combined into an overall test RT-500K (fluctuation testing), RT-485 (CRD internal temperatures) and steady state B-0 tests. It should be noted that no transient tests were conducted above 70% power. b. Inspection Findings (1) QA Monitoring and Audit Intermittent QA Monitoring of the tests was performed and a complete audit of the test results was completed. The audit resulted in a total of 53 findings which resulted in the issuance of five Corrective Action Action Requests (CAAR's). (2) Steam Generator Performance Steam generator steady-state performance at 100% power was considered generally satisfactory. This was based on the Technical Review Committee's determination that RT-500 testing parameter operating limitations had effected the test results. (3) Primary Coolant System Impurities The impurities measured at 100% power were considered by the Technical Review Committee to be satisfactory. However, hydrogen data was not available due to a ga:. chromatograph equipment outage. Overall purification train performance was generally satisfactory; however, there were indications of impurity break-through of the purification train. (4) PCRV Liner Cooling Total liner heat load was measured to be 14.7 x 106 Btu /hr which is consistent with computed values of 16.1 x 106 Btu /hr. Hot Spot tube temperature rises were consistent with the values stated in the Public Service Company letter P-78037. Those tubes exhibiting higher than expected delta temperatures were: Core Support Floor Peripheral Seal Area F5T47 440 F 3S9 210F F6T44 350 F F7T43 370F Cove Outlet T/C Penetration F12T46 440F Area F11T45 350 F 7S93 210 F
f ~ . 9 F7T2 230 F Top Penetrations F9T14 23 F R-5-1 210 F F4T21 210 F R-7-2 220 F (5) Helium Leak Rate The helium leak rate continues to be higher than desired. The primary source of leakage is the helium leak into the reheat steam system by way of the loop 2 steam generator interspaces. The principal leak is throuah steam generator B-2-3 reheat system. However, PSC considers the results of this test generally satisfactory. (6) Circulator Primary Coolant System Primary coolant flow was about10% to 13% higher than anticipated. The pressure rise was 31% to 48% lower than expected and the measured delta pressure across the core 53% lower than expected. However, the results were determined to be satisfactory by the Technical Review Committee and were due to the choice of operating points which were dictated by performance of the fluctuation test RT-500. (7) Nuclear Instrument Calibration Indicated reactor power was 856 Mt4T (102%) and actual was 814 MWT (96.5%). The Technical Review Committee has indicated that the primary problem area for calculating actual power level is in the area of feedwater flow accuracies. (8) Core Region TC Calibration The results from this test were considered satisfactory. However, additionai confirmatory data is to be obtained from fluctuation monitorino data. Previous Core Outlet Thermocouple Traverses recorded in tests RT-509 and RT-524
will also be reviewed. ' i (9) Feedwater Flow Calibration The analytical results of the data indicate that a more detailed plan should be developed to deterrine the variables and ranges which contribute to feedwater flow determinations. Public Service Company will prepare and issue a test to continue data collection and analysis to resolve the feedwater flow rate issue. _-
I l . . . 10 (10) Radioactive Gas Analysis Samples were not obtained for this analysis due to blockage of the sample line. Further analysis of the primary coolant will be obtained by the routine surveillance program as well as Public Service Company tests as required. These should be utilized to substantiate recent data which indicate a level 1/10th of the anticipated values. (11) Iodine Analysis The Iodine Analysis test was in progress at the time the plant was shutdown on November 9, 1981, and no complete data was collected. The test is to be repeated at 100% power. No violations or deviations were identified. 9. Review of Licensee Event Reports The NRC inspector reviewed licensee event reporting activities to verify that they were in accordance with Technical Specification, Section 7, including identification details, corrective action, review and evaluation of aspects relative to operations and accuracy of reporting. The following reports were reviewed by the inspector: 80-60 81-50 81-61 80-73 81-52 81-62 81-22 81-53 81-63 81-38 81-54 81-64 81-45 81-56 81-69 81-46 81-57 81-71 81-48 81-58 81-73 81-49 81-59 81-74 10. Review of Plant Operations The NRC inspector reviewed the corrective action aspect of facility operations to determine if they were being accomplished in accordance with regulatory requirements. Reviewed were all of the licensee event reports generated which had not been closed prior to this report. Included in the review were trends and recurring failuras and the resolution of discrepancies involving safety-related equipment. No violations or deviations were identified. 1 __
r- .. . - 11 11. Report Reviews The NRC inspector reviewed the following report for content, reporting requirements, and adequacy: Monthly Operating Information Report, January 1982 No violations or deviations were identified. 12. 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. . }}