ML20198A380
| ML20198A380 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/12/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20198A360 | List: |
| References | |
| NUDOCS 8605210070 | |
| Download: ML20198A380 (12) | |
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- ~, o UNITED STATES 8" ' ,n NUCLEAR REGULATORY COMMISSION
'5 h E WASHINGTON, D. C. 20555
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CONSUMERS POWER COMPANY DOCKET NO. 50-155 RIG ROCK POINT PLANT AMENDMENT ~TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-6
- 1. The Nuclear Reculatory Commission (the Commission) has found that:
A. The application for' amendment by Consumers Power Company (the licensee) dated July 30, 1984 as revised by submittal dated May 24, 1985 complies with the standards and requirements of the Atomic Eneray Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable. assurance (i) that the activities authorized by this amendment can be conducted without endangerino the health and safety of the oublic; and (ii) that such activities will be conducted in compli-ance with the Commission's reaulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8605210070 860512 PDR ADOCK 05000155 p PDR i
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraphs 2.C.(2) of Facility Operating License No. DPR-6 are hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A '
as revised through Amendment No.85 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATOSY C0F ISSION f f iloh A. Zwolinski, Director RWR ro.iect Directorate #1 Divi. ion of BWR Licensing
Attachment:
Chanoes to the Technical Snecifications Date of Issuance: May 12. 1986.
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ATTACHMENT TO LICENSE AMENDMENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 1-2a 1-2a 10-8 10-8 10-11 10-11 10-14 10-14 10-15 10-15 10-16 10-16 10-17 10-17 10-18 10-18 10-21 10-21 F
s 1.2.8 ,0PERABLE - OPERABILITY - a system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of per-forming its specified safety function (s). Implicit in.this definition shall be the assu=ption that all necassary attendant instrumentation, controls, electrical power sources, cooling or seal water, ISbrication or other auxiliary equipment that is required for the system, subsystem. train, component or device to perform its safety function (s) are also capable of performing their related support function (s).
1.2.9 CHANNEL CALIBRATION -Ladjustments, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The channel calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Chsanel Functional Test. The channel calibration may b.e performed by any series of sequential, overlapping, or total channel steps ruch that the entire ch'annel is calibrated.
1.2.10 CHANNEL CHECK - the qualitative assessment of channel behavior during operation by observation. The determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same par'ameter.
1.2.11 CHANNEL FUNCTIONAL TEST
- a. Analog Channels - the injection of a signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.
- b. Bistable Channels - the injection of a signal into the sensor to verify operability including alarm and/or trip functions.
1.2.12 SOURCE CHECK - the qualitative assessment of channel response when the channel sensor is exprats to a source of increased radioactivity.
1.2.13 MEMBERS OF THE PUBLtG - i;. a des all persons who are not occupationally associated virh the plant.
1.2.14 REPORTABLE EVENT - any of those conditions specified in Section 50.73 to 10 CFR Part. 50.
l l-2a Amendment No. pd', JY', 78, 85
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ADMINISTRATIVE CONTROLS
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ALTERNATES 6.5.1.3 Alternate nembers of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis. However, no more than two alternates shall participate as voting members at any one time in PRC activities.
MIETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calendar month, with special meetings as required.
QUORUM 6.5.1.5 A quorun for PRC shall consist of the Chairman and four (4) voting menbers.
RESPONSIBILITIES 6.5.1.6 The PRC shall be responsible for:
- a. Review of: (1) all procedures required by Technical Specification 6.8 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety. /
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed changes to Appendix "A" Technical Specifications.
- d. Review of all preposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e. Investigation of all violations of the Technical Specifications. (A report shall be prepared. covering evaluation and recommendations to prevent recurrence and forw:rdec to the Vice President Nuclear Operations and to the Director - Nuclear Safety.) ,
i f. Review of plant operations to detect potential nuclear safety l hazards.
- g. Review of reportable events as defined in Section 1.2.14.
- h. Performance of special reviews and investigations and reports thereof as requested by the Plant Superintendent or Chairman of NSB.
- 1. Review of the Site Emergency Plan and implementing procedures.
10-8 AmendmentNo.[,yI, 85 i -_ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - _ _ _ _ - _
ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.2.6 NSB shall meet at least once per calendar quarter during the initial
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year of facility operation following fuel loading and at least once every six months thereaf ter.
' QUORUM 6.5.2.7 A quorum of NSB shall consist of the Chairman and four .(4) members.
(The Vice Chairman may be a voting member when not acting in the capacity of Chairman.) No more than a minority of the quorum shall have line responsibility for operation of the facility. It is the responsibility cf the Chairman to ensure that the quorum convened for a meeting contains appropriately qualified members or has at its disposal consultants sufficient to carry out the review functions required by the meeting agenda.
6.5.2.8 RESPONSIBILITIES REVIEW
'6.5.2.8.1 NSB shall be responsible for the review of:
- a. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affe.ct nuclear safety.
- b. All reportable events and other violations (of applicable statues, codes, regulations, orders, Technical Specifications,
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license requirements or of internal procedures or instructions) having nuclear safety significance.
- c. Issues of safety significance identified by the Plant l Superintendent, the NSB Chairman, Director - Nuclear Safety l or the PRC.
- d. Proposed changes in the operating license or Appendix "A" Technical Specifications.
- e. The results of actions taken to correct deficiencies identified by the audit program specified in Specification 6.5.2.8.2 at least once every six months.
- f. Safety evaluations for changes to procedures, equipment or systems and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.
- g. Maintain cognizance of PRC activities through ISEG attendance at scheduled and special PRC meetings or through review of PRC meeting minutes.
C. 10-11 Amendment No. )d, pd,Jd , 85 1.
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ADMINISTRATIVE CONTROI,5 Superintendent shall appreve,such procedures and changes prior to implementation.
6.8.3 Te=porary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of the original procedure is not altered.
- b. The change is approved by two cembers (or designated alternates) of
- - the PRC, at least one of whom holds a Senior Reactor Operator's License.
- c. The change is documented, reviewed by the PRC at the next regularly scheduled meeting and approved by the Plant Superintendent.
6.9 REPORTING REQUIREMEhrS ROUTINI REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be sub=itted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted:
' START-UP REPORT 6.9.1.1 A summary report of plant start-up and power escalation testing shall be sub=itted following: (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level,'(3) installation of' fuel that has a dif ferent design or has been manuf actured by a different fuel supplier and .
(4) modifications that.may have significantly altered the-nuclear, thermal or by-draulic. performance of'the plant.
6.9.1.2 The stgrt-up report shall address each of the tests identified in the .
Final Hazards Su==ary Report and shall include a description of the measured
. values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica:icns. Any corrective acticns that were required to cbtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
'6.9.1.3 Start,-up reports shall be submitted within: (1) 90 days following com-pletion of the start-up test program, (2) 90 days following resu=ption or com-mencement of commercial power operation or (3) 9 months following initial criticality, whichever is earliest. If the start-up report does not cover all three events (ie, initial criticality, completion of start-up test program and resumption or commencement of commercial operation), supplementary reports shall be' submitted at least every three months until all three events have been com-plated.
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10-14 Amendment No.,ffI, 43, 85
ADMINISTRATIVE CONTROLS AhN. UAL REPORT 5 6.9.1.4 &n annual report covering occupational exposure for the previous calendar year shall be submitted prior to March 1 of each year, i 6.9.1.5 Raports required on an annual basis shall include: l I
- a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 area /yr and their associated manrem exposure according to work and job functions;8 ag, reactor operations and surveillance, inservice inspection, rentine maintenance, special maintenance (describe ^ maintenance), vaste processing and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD or film badge measurements. Small exposures totaling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received froe external sources should be assigned to specific major work functions.
MohTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, US Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
(Section 6.9.1.7 Deleted)
(Section 6.9.1.8 Deleted)
(Section 6.9.1.9 Deleted) 8 This tabulation. supplements the requirement of $20.407 of 10 CFR, Part 20.
10-15 Amendment No. 9, Jg, g), 85
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10-16 Amendment No. 6Y, 85 i
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10-17 Amendment No. 63, //, 85 i
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. ADMINISTRATIVE CONTROLS 6.9.2 UNIQUE REFORTING REQUIREMDITS 6.9.2.1 Annual Radiological Environmental Operating Report Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The annual radiological env'ironmental operating reports shall include summaries, interpretation and statistical evaluation of the
, results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational 4 studies, operational controls (as appropriate) and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use census required by Specification 13.2.3.
l i The annual radiological environmental operating reports shall l include summarized and tabulated results of all radiological j
environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall.be submitted as soon as possible in a supplementary report.
The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by the Specification 13.2.3., and results of the interlaboratory comparison program required by Specification 13.2.4,.
10-18 AmendmentNo,g, 85
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l l ADMINISTRATIVE COS"IROLS l
- b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items 'of equipment related to nuclear safety.
- c. Reportable events as defined in Section 1.2.14.
- d. Records of surveillance activities, inspections ,suui calibrations required by these Technical Specifications.
- e. Records of changes made to the Operating Procedures. ,
- f. Records of radioactive shipments.
- g. Records of sealed source leak tests and results.
- h. Records of annual physical inventory of all source material of record.
. 6.10.2 The following records shall be retained for the duration of the f acility .
cperating license:
- a. Record and drawing changes reflecting facility design modifications made to systems and equip = ant described in the FHSR.
- b. Records of new and irradiated fuel inventory, fuel transfers and as-se=bly burnup histories. _
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- c. Records of monthly facility radiation and centamination surveys.
- d. Records of radiation exposure for all individuals entering radiation control areas.
- e. Records of gaseous and liquid radioac'tive material released to the environs.
- f. Records of transient or operational cycles for those facility components designed for a limited nu=ber of transients or cycles.
- g. Records of inservice inspections performed pursuant to these Technical Specifications.
- h. Records of Quality Assurance activities required by the QA Manual to' be retained for the duration of the Facility Operating License..
- 1. Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59. .
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- j. Records of meetings of the PRC and NSB. I 10-21 Amendment No. 68, 85 ;
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