ML20155D716

Safety Evaluation Supporting Util 840730 Proposed Amend to License DPR-6,changing Tech Specs to Add Definition for Reportable Event & to Delete Specific Reporting Requirements Included in 10CFR50.72 & 50.73

ML20155D716
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/11/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20155D698	List: ML20155D695 ML20155D716
References
NUDOCS 8604170407
Download: ML20155D716 (11)

Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. TO FACILITY OPERATING LICENSE NO. DPR-6 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155

1. Introduction The Nuclear Regulatory Commission, on August 29, 1983, in Federal Register, Volume 48 No. 168, amended its regulations, 10 CFR 50.72 and 50.73, to revise immediate reporting requirements and to establish a new reporting system for significant events at nuclear power plants. On December 19, 1983, the Division of Licensing issued Generic Letter No. 83-43, Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications (STS), informing all licensees of the revision to Section 50.72, Immediate Notification Requirements, and the addition of a new Section 50.73, Licensee Event Report System. The licensees were requested to update their Technical Specifications (TS) to include the new requirements and model STS were provided showing the

. revisions that should be made in the " Administrative Control" and

" Definition" sections. The letter also requested the licensees to review and update other areas of the TS concerning reportability, as required.

On July 30, 1984, Consumers Power Company (the licensee) submitted a proposed amendment to the Technical Specifications (TS) of Facility Operating License No. DPR-6 for the Big Rock Point Plant (BRPP). The proposed amendment adds the definition Reportable Event and adds it to appropriate paragraphs and deletes specific reporting requirements that are now included in 10 CFR 50.72 and 50.73. On May 24, 1985, the licensee submitted a new paragraph number for the definition, Reportable Event, due to an intervening amendment and changed the number on appropriate pages.

A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on ( CFR ). No public comments or requests for hearing were received.

2. Evaluation The proposed changes to TS submitted by the licensee in response to Generic Letter 83-43 were similar to the model STS provided in the letter. In addition the licensee had reviewed TS sections other than the Administrative and Definition sections to update other reporting requirements and references to bring them into line with the new regulations.

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The immediate reporting requirements of 10 CFR 50.72 are not cited in the TS since these regulations stand by themselves and inclusion in TS would be redundant. The new Licensee Event Report System of 10 CFR 50.73 has been included by providing the definition of the new term " Reportable Event," deleting the cbsolete term " Reportable Occurrence;" and by deleting Sections 6.9.1.7, Reportable Occurrences, 6.9.1.8 Prompt Notification with Written Followup and 6.9.1.9, Thirty-Day Written Reports, and all references to these deleted sections.

The above changes were made by modifying the following TS Section 10, Administrative Control pages 10-8, 10-11, 10-14, 10-15, 10-16, 10-17, 10-18, 10-21, and Definition, page 1-3. The staff has reviewed these changes and find that they conform to the model TS provided with Generic Letter 83-43.

We have reviewed the above changes and find that they are administrative in nature and have no affect on safety. Therefore, we find the changes to be acceptable.

3. Environmental Consideration This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4. Conclusion We have concluded, based on the considerations discussed above, that (1) because that amendment does not involve a significant increase in the probability or consequences cf an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operations in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Dated:

The following personnel have contributed to this Safety Evaluation:

K. R. Ridgway 2

Docket No. 50-155 TAC No. M55536 Plant: Big Rock Point SYSTEMATIC ASSESSMENT"0F LICENSEE PERFORMANCE Criteria Category Rating

1. Management Involvement and Control in Assuring Quality 1 The licensee shows consistent evidence of planning, scheduling, and control of licensing activities.

2. Approach to Resolution of Technical Issues From a N/A Safety Standpoint

3. Responsiveness to NRC Initiatives 1 The licensee made timely responses to requested changes and updated TS pages for intervening amendments.

4. Enforcement History N/A

5. Operational and Construction Events N/A

6. Staffing (including Management) N/A Refer to Part II, Table 1, NRC Appendix 0516, for guidance in determining appropriate categories.

1.2.14 Reportable Event - any of those conditions specified in Section 50.73 to 10 CFR Part 50.  ;

2.0 SITE 2.1 LOCATION - obs11 be in Charlevoix County, Michigan, shall be about 4 miles northeast of Charlevoix, Michigan, and shall be about 11 miles west of Petoskey, Michigan.

2.2 BOUNDARIES - shall surround about.600 acres, and the nearest landside property line shall be about 2680 feet, and the nearest shoreline property line shall be about 200 feet from the plant's containment sphere.

2.3 PRINCIPAL ACTIVITIES - ahall be those associated with the operation of the Big Rock Point Nuclear Plant and may include other activities directly connected with the generation, transmission and distribution of electric energy.

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l 1-3 Amendment No. $$, 77, 7$

_ ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 Alternate members of the FRC 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 sctivities.

MEETING 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 quorum for PRC shall consist of the Chairman and four (4) voting members.

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.

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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 proposed changes or modifications to plant systems or equipment that affect nuclear safety.

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e. Investigation of all violations of the Technical Specifications. (A report shall be prepared covering f evaluation and recommendations to prevent recurrence and l forwarded to the Vice President Nuclear Operations and to ,

the Executive Engineer, NAPO.)

f. Review of plant operations to detect potential nuclear safety 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 roergency Plan and implementing procedures.

PRC review may be performed through a routing of the itec subject to the requirements of Specification 6.5.1.7. l l

10-8 Amendment No. $$, $3, /$

4 ADMINISTRATIVE COhTROLS MEETING FREQUENCY 6.5.2.6 NSB shall mest at least once per calender quarter during the ir.itial year of facility operation following fuel loading and at least once every six mor.ths thereafter, i 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 of 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 J

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 affect nuclear safety.

b. All reportable events and other violations (of applicabis 2

statutes, codes, regulations, orders. Technical Specifications, license requirements or of internal procedures or instructions) having nuclear safety significance,

c. Issues of safety significance identified by the Plant Superin-

tendent, the NSB Chairman, Executive Engineer NAPO 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 l 1 east once every six months.

f. Safety evaluations for changes to procedures, equipment or systems and tests or experiments completed under the provisions i of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.

, 3 Maintain cognizance of PRC activities through NAPO attendance at scheduled PRC meetings or through review of PRC meeting minutes.

10-11 Amendment No. 46, 63, 76 4

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ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures cf 6.8.1 above may be provided:

a. The intent of the original procedtre is not altered,

b. The change is approved by two members (or designated alternates) of the PRC, at least one of whom holds a Senior Reector 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 REQUIREMENTS ROUTINE REPORTS j 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted 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 submitted 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 different design or has been manufactured by a different fuel supplier and (4) modifications that may have significantly altered the nuclear, thermal orhy-draulic performance of the plant. .

6.9.1.2 'Ibe start-up report shall address each of the tests idenified in the Final Hazards Summary 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 specifications. Any corrective actions that were required to obtain 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-plation of the start-up test program, (2) 90 days following resumption 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 sh'all be submitted at least every three months until all three events have been com-plated.

10-14 Amendment No. $$, $3

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ADMINISTRATIVE CONTROLS ANNUAL REPORTS 6.9.1.4 An annual report covering occupational exposure for the previous calendar i

year shall be submitted prior to March 1 of each year.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, j utility and other personnel (including contractors) receiving i exposures greater than 100 arem/yr and their associated manrem exposure according to work and job functions; eg, reactor opeia+. ions and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste 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 j dose received from external sources should be assigned to l specific major work functions.

MONTHLY OPERATING REPORT ,

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'. 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 follcwing 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) f 8

This tabulation, supplements the requirement of $20.407 of 10 CFR, Part 20.

10-15 Amendment No. 9, f$, $3 h

(Pages 116 & 117 deleted)

ADMINISTRATIVE CONTROLS 6.9.2 UNIQUE REPORTING REQUIREMENTS A. Radioactive Effluent Release A report shall be submitted to NRC within 60 days after January 1 and July 1 of each year specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid and gaseous affluents during the previous 6 months. The format and content of the report shall be in accordance with Regulatory Guide 1.21, Revision 1, dated June 1974.

1. Gaseous Effluents

a. Gress Radioactivity Releases (1) Total gross radioactivity (in curies), including noble and activation gases released.

(2) Maximum gross radioactivity release rate during any one-hour period.

(3) Total gross radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed.

(4) Percent of Technical Specifications limit.

b. Iodine Releases (1) Total iodine radioactivity (in curies) by nuclide relea;ed, based on representative isotopic analyses l performed. l l

(2) Percent of Technical Specifications limits for I-131 released.

c. Particul' ate Releases (1) Gross radioactivity ($, T) released (in curies) excluding background radioactivity.

10-18 Amendment No. $3, 77 l

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ADMINISTRATIVE CONTROLS 4 b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

d c .' Reportable events as defined in Section 1.2.14.

d. Records of surveillance activities, inspections and 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 facility operating license:

a. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the FHSR. .

b. Records of new and irradiated fuel inventory, fuel transfers and i assembly burnup histories.

c. Records of monthly facility radiation and contamination surveys.

d. Records of radiation exposure for all individuals entering radiation

, control areas.

e. Records of gaseous and liquid radioactive material released to the environs.

f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

3 Records of inservice inspections performed pursuant to these l Technical Specifications. l

h. Records of Quality Assurance activities required by the QA Manual to be retained for the duration of the Facility Operating License.

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1. Records of reviews performed for changes made to proc'edures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

j. Records of meetings of the PRC and NSB.

l 10-21 Amendment No. $3

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