ML20215A581
| ML20215A581 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/29/1977 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Switzer D NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| References | |
| RTR-REGGD-01.016, RTR-REGGD-1.016 TAC-30204, NUDOCS 8706160715 | |
| Download: ML20215A581 (8) | |
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.F UNITED STATES yV "t
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 h'#
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July 29, 1977 Dockets Nos. 50-245 and 50-336 Northeast Nuclear Energy Company ATTN: Mr. Donald C. Switzer President P. O. Box 270 Hartford, Connecticut 06101 Gentlemen:
s RE: MILLSTONE NUCLEAR POWER STATION UNITS NOS. 1 AND 2 In October 1974, we initiated a program to update the reporting requirements specified in technical specifications of power reactor licensees. Regulatory Guide 1.16, " Reporting of Operating Informa-tion - Appendix A Technical Specifications" was the basis for the reporting requirements. Licensees were issued specifications that either refer to Regulatory Guide 1.16 or utilize words from certain sections of Regulatory Guide 1.16.
You are one of a few licensees that reference the Regulatory Guide.
We w' uld'like to replace your reference to Regulatory Guide 1.16 with o
words from Regulatory Guide 1.16 that are appropriate and applicable.
This change would delete mandatory reporting of Events of Potential Public Interest and use of reporting forms contained in the referenced Regulatory Guide.
We request that within 45 days you propose Technical Specifications that utilize words from Regulatory Guide 1.16.
Sample technical i
specifications are enclosed for your use.
Your present technical specifications require that for each reportable occurrence you use the format presented in the guide and the instructions found in " Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File", 00E-SS-001, October,1974.
The format for the Licensee Event Report has been modified to make the LERs more useful for evaluation purposes.
In addition, new instructions for completing the LER have been prepared and may be found in " Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File", NUREG-0161, July 1977. Two copies of this new instruction manual are enclosed for s
your future use.
For additional copies of the instruction manual or blank LER forms, please contact our Director of Management Information and Program Control.
O B706160715 770729 90R ADOCK 050 45
4 Northeast Nuclear Energy Company g The new instruction manual contains a facsimile of the revised LER and instructions which are very similar to those presently being used.
One difference is that in addition to the filled in LER form, we request that you provide a complete narrative report of the event for all 14 day follow-up reports. The narrative report should contain sufficient information to permit full understanding and enable a safety assessment of the event to be made. For the 30 day report, a well written LER within the space limitations of the LER may be adequate.
Therefore, we request that you review the enclosed instruction manual and make plans to use the revised form and instructions for the first reportable occurrence after the issuance date of new technical specifications.
Sincerely, os George Le,ar, Chief Operating Reactors Branch #3 O-Division of Operating Reactors-
Enclosures:
1.
Sample Technical Specifications 2.
Instruction Manual cc: William H. Cuddy, Esquire Day, Berry & Howard Counselors At Law One Constitution Plaza Hartford, Connecticut 06103 Anthony 2. Roisman, Esquire Roisman, Kessler and Cashdan 1025 15th Street, N. W.
5th Floor Washington, D. C.
20005 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 Northeast Nuclear Energy Company ATTN:
Superintendent Millstone Plant O
P. O. sex,28 Waterford, Connecticut 06385
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ENCLOSURE N0, 1 SAMPLE TECHNICAL SPECIFICATIONS O-ADMINISTRATIVE CONTROLS 6.9 REPORTING RE0VIRE'1ENTS ROUTINF REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Renulations, the followina reports shall be submitted to the Director of the Reaional Office of Inspection and F.nforcement unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant 'startup and power escalation testina shall be submitted followino (1) receipt of an operatina license, (2) amendment to the license involving a planned increase in oower level, (1) installation of fuel that has a different desian or has been manu-factured by a different fuel sunolier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.
The reoort shall address each of the tests identified in the FSAR and shall include a description of the neasured values of the operatina conditions or characteristics obtained durinq the test oronram Q-and a comparison of these' values with desian predic'tions and specifica-tions. Any~ corrective actions that were required to obtain s.atisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report..
6.9.1.2 Startup reports shall be submitted within (1) 90 days followinn completion of the startun test pronram, (2) 90 days followina resumption or commencement of commercial oower operation, or (3) O months 'ollowinn initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (l.e., initial criticality, conoletion of startuo test pronram, and resumotion or commencement of commercial All STS 6-14 March 15,1977 O
Q ADMINISTRATIVE CONTROLS power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
E ANNUAL OPERATING REPORT 6.9.1.3 Routine operating reports covering the operation of the unit during the previous calendar year shall be submitted prior.to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.4 The annual operating reports shall provide a comprehensive summary of the operating experience gained during the year, even though some repetition of previously reported information may be involved.
References in the annual operating report to previously submitted 5
reports shall be clear.
6.9.1.5 Each annual operating report shall include:
a.
A narrative summary of operating experience during the report period relating to safe operation of the facility, including safety-related maintenance not covered in 6.9.1.5.b.5 below.
For each outage or forced reduction in power U of over twerity'
,Q b.
percent'of. RATED THERMAL POWER where the reduction extends for greater than four hours:
1.
The proximate cause and the system and major component involved (if the outage or forced reduction in power involved equipment malfunction);
2.
A brief discussion of (or reference to reports of) any reportable occurrences pertaining to the outage or power reduction; y A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
2/ The term " forced reduction in power" is defined as the occurrence of a component failure or other condition which requires that the load
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on the unit be reduced for corrective action immediately or up to and including the very next weekend.
Note that routine preventive maintenance, surveillance and calibration activities requiring power reductions are not covered by this section.
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ALL STS 6-15 March 15,1977
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O ADMINISTRATIVE CONTROLS 3.
Corrective action taken to reduce the probability of recurrence, if appropriate; 4.
Operating time lost as a result of the outagg or power reduction (for scheduled or forced outages,- use the generator off-line hours; for forced reductions in power, use the approximate duration of operation at reduced power);
5.
A description of major safety-related corrective main-tenance performed during the outage or power reduction, including the system and component involved and identifica-tion of the critical path activity dictating the length of the outage or power reduction; and 6.
A report of any single release of radioactivity or radiation exposure specifically associated with the outage which accounts for more than 10% of the allowable annual values.
A tabulation on an annual basis of the number of station. -
c.
utility en'd other personnel (including' contractors) receiving exposures greater than '100 mrem /yr and their assocjated mah rem exposure according to work and job functions,1 e.g..'
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
d.
Indications of failed fuel resulting from irradiated fuel examinations, including eddy current tests, ultrasonic tests, or visual examinations completed during the report period.
3/ The term " forced outage" is defined as the occurrence of a component failure or other condition which requires that the unit be removed
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from service for corrective action immediately or up to and including the very next weekend.
4] This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.
ALL STS 6-16 March 15, 1977
Q ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT
.9.1.6 Routine reports of operating statistics and shutdown experience 6hall be submitted on a monthly basis to the Office of Inspection and
- 20555, sEnforcement, U.S. Nuclear Regulatory Commission, Washington, D.C.
with a copy to the Regional Office, to arrive no later than the tenth of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 6.9.1.7 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC.
Supplemental reports may be required to In case of corrected or fully describe final resolution of occurrence.
supplemental reports, a licensee event report shall be completed and 1
reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP The types of events listed below shall be reported within 24 6.9.1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate
.Q no later than the first wor' king day following the' event, with a written followup report within two weeks. The written followup report shall include, as a minimum, a completed copy of a licensee event repo'rt form.
Information provided on the licensee event report form shall be supple-mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
Failure of the reactor protection system or other systems a.
subject to limiting safety system settings to initiate the required protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
b, Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications, Abnormal degradation discovered in fuel cladding, reactor c.
coolant pressure boundary, or primary containment.
O ALL STS 6-17 March 15,1977
ADMINISTRATIVE CnNTROLS d.
Reactivity anomalies involvinn disaqreement with the credicted value of reactivity balance under steady state conditions durino power operation greater than or equal to 1" ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifica-tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if s.uberitical, an unplanned reactivity insertion of more tnan 0.5" ak/k; or occurrence of any unplanned criticality, Failure or malfunction of one or more components which prevents e.
or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR.
f.
Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require-ments of systems require.d to cope with accidents analyzed in the SAR.
Conditions arising from natural or man-made events that, as a a.
direct result of the event require plant shutdown, operation of safety systems, or other protective measures required by O'
technical soecifications.
h.
Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
1.
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica-tions bases; or discovery during clant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or cor-rective neasures to prevent ths existence or development of an unsafe condition.
THIRTY DAY 4RITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Recional office within thirty days of ALL STS 6-18 March 15,1977
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O ADMINISTRATIVE CONTROLS occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
Reactor protection system or engineered safety feature instru-a.
ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems, b.
Conditions leading to opention in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.
Observed inadequacies in the implementation of administrative c.
or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
d.
Abnormal degradation of systems other than'those speci.fied
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.in 6e9.1.8.c above designed to contain radioactive material resulting from the fission process.
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