ML19249E563
| ML19249E563 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/23/1979 |
| From: | Feierabend C, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19249E561 | List: |
| References | |
| 50-282-79-18, 50-306-79-15, NUDOCS 7910010735 | |
| Download: ML19249E563 (10) | |
See also: IR 05000282/1979018
Text
{{#Wiki_filter:Y. - U.S. NUCLEAR REGULATORY COMMISSION ' OFFICE OF INSPECTION AND ENFORCEMENT REGION III Report No. 50-282/79-18; 50-306/79-15 Docket No. 50-282; 50-306 License No. DPR-42; DPR-60 ' Licensee: Northern States Power Company 414 Nicollet Ma'_1 Minneapolis, MN 55401 Facility Name: Prairie Island Nuclear Generating Plant, Units 1 & 2 Ir ypection At: Prairie Island Site, Red Wing, MN Inspection Conducted: July 1-31, 1979 RFO) & Inapector: C. D. Feieraoend $-27.-77 RFtO A Approved By: R. F. Warnick, Chief 4-20-79 Reactor Projects Section 2 Inspection Summary Inspection on July 1-31, 1979 (Report No. 50-282/79-18; 50-306/79-15 Areas Inspected: Routine resident inspection of plant operations, main- tenance, security, review and audit, startup testing after refueling (Unit 1), followup of licensee reported events and IE bulletins. The inspection involved 78 inspector-hours by the resident incnector. Results: Of the seven areas inspected, no items of noncompliance or deviations were found in ,ix areas. One item of noncompliance was found - in one area (Jeficiency (Unit 1) - f ailure to adhere to controls for making changes to test prc 3 dure, parsgraph 7) 7 910 0 3 0 7 3 g ,LJJ h,c Q ~- , .
. DETAILS
1. Personnel Contacted F. Tierney, Plant Manager J. Brokaw, Plant Superintendent, Operations and Maintenance E. Watzl, Plant Superintendent, Plant Engineering and Radiation Protection A. Hunstad, Staff Engineer . R. Lindsey, Superintendent, Operations J. Nelson, Superintendent, >bintenance J. Hoffman, Superintendent, Technical Engineering D. Mendele, Superintendent, Operations Engineering D. Schuelke, Superintendent, Radiation Protection S. Fehn, Senior Scheduling Engineer M. Sellman, Senior Nuclear Engineer R. Conklin, Supervisor, Security and Plant Services G. Sundberg, Instrument Engineer G. Edon, Shift Supervisor P. Valtakis, Shift Supervisor D. Althaus, Shift Supervisor J. Meath, Shift Supervisor D. Walker, Shift Supervisor 2. General Unit I was shut down on July 4, because of turbine vibrations. It was off the line for the rest of the month for repairs to the high pressure turbine. During the *atage the licensee performed inspec- tions of feedwater piping and shell type anchors in response to ir Bulletins 79-02 and 79-13. 3. Plant Operations The inspector reviewed plant operations including examination of selected operating logs, special orders, temporary memos, jumper and tagout logs for the month of July. Tours of the plant included walks through the various areas of the plant to observe operations and activities in progress; to inspect the status of monitoring instruments, to observe for adherence to radiation controls and fire protection rules, to check proper alignment of selected valves and equipment controls, and to review status of various alarmed annunci- ators with operators. The inspector also reviewed annunciator status, recorder charts, surveillance records, and logs to verify that plant operations were maintained in accordance with Technical Specif* cation requirements. -2- p , - ..r. b ) kl
., . No items of noncompliance or deviations were identified. - 4, Security The inspector conducted periodic observations of access control, issuing badges, vehicle inspection, escorting, and communication checks. No items of noncompliance or deviations were identified. 5. ~ Maintenance The inspector observed maintenance activities in progress associated with repairs and temporary modification of the Unit I turbine. No areas of concern were identified. 6. Review and Audit The inspector attended an Operations cammittee meeting on July 19, 1979. The committee completed biennial review of several surveil- lance procedures, preventive maintenance procedures, and section work instructions. The committee also reviewed safety evaluations associated with a scheduled natural circulation .ast and for oper- ations with lower first stage turbine pressure, and approved setpoint changes for steam dump actuation to compensate for lower first stage pressure. The inspector reviewed the minutes of the meeting and verified that they adequately described the decisions made. 7. Startup Testing Following Refueling (Unit 1) The inspector verified that incore physics tests and control rod checks were conducted prior to or during startup and return to power. The following tests were reviewed for availability of procedures and records of test completion: D30 - Post Refueling Startup Testing D31 - Reactivity Computer Checkout D32 - Temperature Coef ficient at Hot Zero Power D33 - Rodworth and Boron Worth Measurement D34 - Beron End Point Measurement D36 - Plant Hect Balance D51 - Temperature Coef ficient at Power The inspector also verified that surveillance tests had been completed prior to startup. -3- 4 n- ,q luJJ U m, o
. SP 1546 Control Rod System Timing - SP 1018 Analog Rod Position - Bank Counter Test SP 1046 Full Length Control Rod Drop Timing SP 1169 Reactor Coolant System Flow Verification Review of the test records and results did not identify any concerns in the scope of the test program or in the results of the testing. As this core includes the first Exxon fuel the licensee will submit a startup report in accordance with Technical Specification 6.7.A.l. The inspector observed testing in progress during routine resident
inspection of plant operations in May, 1979. Activities in progress were being performed in accordance with procedures. No areas of concern were identified. A detailed audit of completed procedures identified some procedural inconsistencies that did not appear to have any significant effect on the test program. These were being discussed with the responsible personnel and supervisors. The inspector observed that the operations committee review of the results of zero power testing prior to increasing power above 5% was not documented in minutes of a subsequent meeting. The inspector verified that a poll had been conducted by reviewing the entry in the test procedure, the nuclear engineers tabulation of results, and confirmation by interview with other operations committee members that the poll was conducted. The audit did identify a deficiency in the areas of procedure changes and documentation of review by the Operations Committee (OC). Several steps in test procedures were omitted as not applicable (NA) without documenting the concurrence of two individuals holding senior operator licenses (SRO's) or review by the OC and a meiber of plant management. An example of this was steps 4.2.8 and 4.2.10 of procedure D30, which increased reactor power to approximately 3% for flux mapping and returned power to zero for continued testing. The inspector had no concern with the technical reasons for eliminating the steps. Failure to follow administrative controls for caking temporary changes to procedures is considered to be noncompliance with Technial Specification 6.5.D. 8. Licensee Event Reports (LERs) The inspector reviewed the following LERs submitted by the licensee, determined that reporting requirements had been met, and determined that corrective actions were being implemented. (Closed) -4- 1';5 n29
. a. P-RO-79-08, No. 11 SI pump failure to auto start.
A design change to add a monitor light to the SI pump control circuit has been approved by the Operations Committee. b. P-RO-79-13, Diesel cooling water pump tripped and locked out during trouble shooting. c. P-RO-79-15, Failure of power range channel. . d. P-RO-79-16, ASME Code Section XI test not scheduled. This was identified and reviewed during a previous inspection.1/ c. P-RO-79-18, Missed SP1187 in January 1979. This was a weekly battery inspection that was missed because of 5 weeks in the month, f. P-RO-79-19, Discovery that containment purge valves not analyzed for dynamic loading. The inspector verified that the licensee had taken action to prohibit purging except during cold shutdown. The licensee will notify NRR of resolution prior to resuming purging during normal operation. g. P-RO-79-21, Unit 1 loop 3 steam generator level transmitter observed to be responding slowly. The inspector observed the level indication and trouble shooting activities before and after repairs had been completed. 9. IE Bulletins IEB 78-04, Environmental Qualification of Certain Stem Mounted a. Limit Switches Inside Containment The inspector confirmed that the licensee had completed replace- ment of the limit switches in Unit 2 during the December, 1978 refueling outage and in Unit 1 during the April, 1979 refueling outage (Closed). b. IEB 79-01, Environmental Qualification of Class 1E Equipment The licensee reply ! escribes actions taken. (Closed) d If IE Inspection Report No. 50-306/79-09. 2/ NSP letter to OIE dated June 12, 1979. -5- a n ! - v - }) .)
. IEB 79-02, Pipe Support Base plate Designs Using Concrete
c. Expansion Bolts The inspector observed areas of containment where pull testing was being performed and examined one of the two anchors that did not pass the pul.1 test. The anchor was one of four using 7/8 inch bolts to anchor snubber number 1-SIRil-23, which pulled out at 3,000 lbs. The test for safety factor of PU/5 was to be 3770 lbs. Analysis verified that the three remaining bolts adequately anchored the snubber without considering the anchor that failed the tests. Examination of the shell anchor indicated , that it had not been fully seated and expanded. Repairs consisted of replacement and retesting. Another shell type anchor was observed to be loose on snubber 1-RCS!!-81. It had not been adequately set. The total design load for this anchor was 408 lbs. Each of the four 3/4 inch anchor bolts has adequate design to hold much more than the design load for the snubber. The anchor was replaced and satisfactorily tested. These were the only two failures of pull tests for the shell type anchors after completion of more than 450 pull tests in both units. The licensee considers this to be adequate demon- stration of satisfactory installation of shell type anchors, but will perform pull tests on a sampling basis in Unit 2 containment during the next refueling outage. (0 pen) 10. Exit Interviews The inspector attended exit interviews conducted by IE III regional based inspectors: M. J. Oestmann - July 13, 1979 W. S. Little, I. N. Jackiw, F. T. Daniels - July 13, 1979 The inspector met weekly with licer te representatives and with Mr. F. Tierney at the conclusion o the inspection. The inspector summarized the scope and findings the inspection. One item of noncompliance was identified. Thi. was a deficiency in failure to adhere to prescribed controle for making temporary changes to a test procedure. Enclosures: Preliminary Inspection Findings -6- - <o i {o JJ pJ s , '
., - 0FFICE OF INSPECTION AN*' IN"J50 M PRT.LIMINARY INSPECTION FINDINGS - - , . . _ . :- : ._ _. -- - - - , . - - _ , 2. REC 10NAL OFFICE 1. LICENSEE Northern States Power Company U.S. Nuclear Regulatory Commission 414 Rico11et ?hil Office of Inspection & Enforcenent, RIII Minneapolis, MN 55401 799 Roosevelt Road Glet Ellyn, IL 60137 Prairie Island 1 (Redwing, MN) Prairie Island 2 (Redwing, MN) 3. DOCKET NW.BERS 4. LICENSE NUM3ERS 5. DATE OF INSPECTION 50-282; 50-306 DPR-42: DPR 60 7 gg- 6. k'ithin the scope of the inspection, no items of no pli e or deviation '}' were found. 7. The following m.atters are preliminary inspection findings: . @B' . . . These preliminary inspection findings vill be reviewed by NRC Supervision / f-{ 8. Management at the F.egion III Office and they will correspond with you concerning any enforcement action. g - '
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. OFFICE OF INSPECTION AN." IS."J.t J:E. .' . . PRELIMINARY INSPdCTION FINDINCS_ / - - - - - - - ... ...... , .. ._- . ~ . . - g 2. REC 1011AL OFF1CE 1. LICENSEE U.S. Nuclear Regulatory Com.nission Northern States Power Company Office of Inspection & Enforcement RIII 414 Nicollet Mall 799 Roosevelt Road ?finneapolis, MN 55401 Glen Ellyn. IL 60137 Prairie IsNd 1 (Redwing, MN) Prairie Island 2 (Redwing, MN) - 4. LICENSE NUMBERS 5. DATE OF INSPECTION 3. DOCKET NUMBERS p, // g 50-282; 50-306 DPR-42: DPR 60 pli e or deviation Within the scope of the inspection, no items of no ]\\ 6. vere found. The following ru.tters are preliminary inspection findinge: 7. , I
'I h g $N ' o . . . . These preliminary inspection findings will be reviewed by NRC Supervision / . 8. Management at the Region III Office and they will correspond sith ou f concerning any enforcement action. , / ' Nuclear segulatory Commissidn Inspector n/1 p77?) 4 ,f
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, PRELIMINARY INSPECTION FINDINGS . l' ! 2. REGIONAL. OFFICE 1. 1.!CENSEE U.S. Nuclear Regulatory Co==ission Northern States Power Company Office of Inspection & Inforcement, RIII 414 Nicollet Mall Minnaapolis, MN 35401 799 Roosevelt Road ' Glen Ellyn, IL 60137 Prairie Island 1 (Redwing, MN) Frairie Island 2 (Redwing, MN) 4. I.ICENSE NUMBERS 5. DATE OF INSPECTION 3. DOCKET ND:3ERS 50-282; 50-306 DPR-42: DPR 60 jf_ g 0, /gg / J=plianceordeviation Within the scope of the inspection, no ite=s of non ---g 6. were fouad. Il The follow;.ig =atters are preliminary inspection findings: y 7. i D k D D These preliminary inspection findings will be reviewed by NRC Supervision / , 8 at th'e llegion 111 Office arid they will corresp06d with you ' , Manageuient ~' concerning any enforcement action. .. JY ,m / Me'-~z Nuclear Regulatory Concission Inspector ' , 4 O :' .~ b~. ,{ " louJ s.
.. . . PRELIMINARY INS?ECTION ?!NLINOS_ - l' ! 2. RECIONAL 077 CE ' . . LICENSEE Northarn States Power Company f U.S. Nuclear Regulatory Ccanission Office o:. Inspection & Enforcement, R::: - ..8,.,, .. - . * .v . , o . . - - . .o _ . . -- .-.:na3;olis , :0: 5540; 799 noosevelt noce ' ' { Clan Ellyn, IL 60137 ?r irie Is.ond . (Radwing, MN) ?r- rie != lend 2 (Radwing, MN)
?. f - -. 4 'l4. LICENSE NUM3ERS ' S. DAEE 07 !/SPECTION 3. LOCKET NUX3ERS 50-252; 50-306 DPR-42: D?R 60 July 21-31, 1979 liance or deviation <.'ithin the scope of. the- inspection, no items of nonco=p ~~~ 5. """ wCrd found. . . Tha following matters are preliminary inspection findings: -[h, 7. tem-arary chan7,es to procedures Eechnical Specification 6.5.D. requires that change the intent of the original procedure may be made with the which do not concurrence of two individuals holding senior operator licenses. and that such changes shall be documented . reviewed by the Operations Committe and approved by a acaber _f plant management designated by the Plant Manager within one month. Contrary to the above, dscussnuxstare:ni concurrence of individuals holding senior operating licenses, review by Operations Committa and approval by a member of plant manage' ment was not documented for temporary changes made to prccedure D30 - Post Refueling Startup Testing on May 5,.1979. D \\ \\, D h D ss - , Tahoe p7clit.inary inspection findings will ha reviewad by NRC Supervision / , _. 6. 16n 111 Office and they Ulll carrespond Whh you 'j , Mana ge.ac..L At the Red y/ concerning any enforcement action. , f4 A%- Nuc1 car Re(ulatory Consis'sion Inspector . t . & D l i i1 Iv '3) i - s- }}