ML20082D229

Proposed Tech Specs Re Administrative Controls

ML20082D229
Person / Time
Site:	Fort Calhoun
Issue date:	11/16/1983
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20082D219	List: ML20082D215 ML20082D222 ML20082D229
References
TAC-53219, NUDOCS 8311220353
Download: ML20082D229 (14)

Text

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5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The-Manager - Fort.Calhoun Staticn shall be responsible for overall facility operation and shall-delegate in writing the succession to this responsibility during his absence.

5.2' Organ'iuation offsite 5.2.1 The offsite organization for facility management and techni-cal support shall be as shown on Figure 5.1. ,

5.2.2 Plant Staff

.The plant staff organization shall be as shown in Figure 5.2 and function as follows:

a. The minimum number and type of licensed and unlicensed operating personnel required onsite for each shift shall-be as shown in Table 5.2-1.

b. An Operator or Technician qualified in Radiation Pro-tection Procedures shall be onsite when fuel is in the reactor.

c. All core alterations shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to fuel handling.who has no other concurrent responsibilities.during the oper-ation.

d. Fire protection program responsibilities are assigned to those positions and/or groups designated by aster-isks in Figures 5-1 and 5-2 according to the pro-cedures specified in Section 5.8 of the Technical Specifications.

e. A fire brigade consisting of 5' members shall be main-tained onsite at all-times.# - The fire brigade shall not include the minimum shift crew necessary for safe.

shutdown of the unit 1(2 members).

1. . Fire Brigade' composition may be less'than the minimum requirements forta period.of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade members provided immediate action'is'taken to restore the Fire' Brigade to within the minimum requirements. '8311220353 831118 PDR ADOCK 05000285 P PDR

' Amendment No. pf, ps, 76,'J8', 53 5-1 ATTACHMENT A

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. TABLE 5.2-1 1 MINIMUM SHIFT CREW COMPOSITION (ii) .

Cold Shutdown or Operating or License Hot Shutdown Modes

' Category Core Alteration Refueling Shutdown Senior Operatbr 2(iii)

License 1(i) 1 o

Operator 2 1 2(iv)

License 1 2 Non-Licensed (As required)

Shift = Technical None 1 Advisor None (i) Does.not include individual with Senior Operator License super-vising Refueling Operations.

(ii) ' Shift crew composition may-be one less than the minimum require-ments for a period of' time not tb exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to ac-ccumodate unexpected absence of on-duty shift crew members pro-vided immediate action is taken to restore the shift crew com-position.to within the minimum requirements of Table 5.2-1.

This provision does not permit any shif t crew position to be un-manned upon shif t charige due to an oncoming shift crewman being late or absent.. (

(iii) At least one of these individuals mustJbe in the control room i ' ' 'i at all times.

(iv) At least one of these individuals or the second senior licensed operator if both senior licensed operators are in the' control room must be present at the controls at all times.

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Amendment No. M J4, 54 5,-2

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i 5.0 ADMINISTRATIVE CONTROLS 5.5.2.8 e. The Fort Calhoun Station Emergency Plan and imple- l menting procedures at least once every twelve '

l months. .i

f. The Site Security Plan and implementing procedures at least once every twelve months.

g. The Safeguards Contingency Plan and implementing pro-cedures at least once every twelve months.

h. Any other area of facility operation considered ap-propriate by the Safety Audit and Review Committee or the Assistant General Manager - Production Oper-ations, Fuels, and Quality Assurance & Regulatory Af-fairs.

Authority 5.5.2.9 The Safety Audit and Review Committee shall report to and advise the Assistant General Manager - Production Oper-ations, Fuels, and Quality Assurance & Regulatory Affairs on those areas of responsibility specified in Sections

-5.5.2.7 and 5.5.2.8.

Records

.5.5.2.10 Records of Safety Audit and Review Committee activities shall be prepared, approved and distributed as indicated

< below:

a. Minutes of.each Safety Audit and Review Committee meeting shall1be prepared, approved and forwarded to the Assistant General Manager - Production Oper-ations, Fuels, and' Quality Assurance & Regulatory Af-fairs within 14 days following each meeting.

b. Reports of reviews encompassed by Section 5.5.2.7 e, f, g, and h above shall be prepared, approved and forwarded to the Assistant General Manager - Pro-duction Operations, Fuels, and Quality Assurance &

Regulatory Affairs-within 14 days following com-pletion of the review.

c. Audit reports encompassed by Section 5.5.2.8 above shall be . forwarded to the Assistant General Manag-er - Production Operations, Fuels, and Quality Ae-surance & Regulatory Affairs and to the responsible management positions designated by the Safety Audit and Review Committee within 30 days after completion of-the audit.

Amendment No. M ,16, 36, 60 5-8

5.0 ADMINISTRATIVE CONTROLS

-5.5.3 Fire Protection Inspection

a. An independent fire protection and loss prevention i nspection and audit shall be performed annually uti-lizing either qualified off-site licensee personnel or an outside fire protection firm. The audit and inspection program responsibility shall rest with the Safety Audit and Review Committee.

b. An inspection and audit of the fire protection and loss prevention program by an outside qualified fire consultant shall be performed at intervals no great-er than 3 years.

5.6 Deleted - left open intentionally 5.7 Deleted - left open intentionally 5.8 Procedures 5.8.1 Written procedures and-administrative policies shall be es-tablished, implemented and maintained that meet or exceed the minimum requirements of sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix A of USNRC Regulatory Guide 1.33 except as provided in 5.8.2 and 5.8.3 below.

Each' procedure and administrative policy of 5.8.1 above,

-5.8.2 and changes thereto, shall be reviewed by the Plant Review Committee and approved by the Manager - Fort Calhoun Station prior to implementation and periodically as set forth in each document.

5.8.3 Temporary changes to procedures 5.8.1 above may be made provided:

Amendment No. I, 46 , 38 5-9

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5.9.1 Continued work and job functions,3/ e.g., reactor operations and surveillance, inservice inspection, routine mainte-nance, special maintenance (describe maintenance),

waste processing, and refueling outages. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measure-ments. 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.

c. Monthly Operating Report. Routine reports of oper-ating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.S.

Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the appropriate Regional Office, to arrive no later than the fifteenth of each month following the calendar month covered by the report.

This monthly report shall also include a statement regarding any challenges to the pressurizer power operated relief valves or safety valves occurring during the subject month.

5.9.2 Reportable Occurrences The following notifications and reports are required by 10 CPR 50.36 (Safety Limits and LCO's), 10 CFR 50.72 (Signifi-cant Event Reports), 10 CFR 50.73 (LER Reports), 10 CFR 20.402 (Stolen or Lost Licensed Material Reports), 10 CFR 20.403 (Immediate Radiological Reports), and 10 CFR 20.405 (30 Day Radiological Reports).

a. One (1) Hour Notification Following Significant Events Notification.chall be made to the NRC Operations Center via the Emergency Notification System within one (1) hour of discovery of the occurrence af any of the following events:

NOTE: If the Emergency Notification System is in-operative, notification (s) shall be made via com-mercial telephone service, other dedicated telephone system, or any other method which will ensure a report is made as soon as practical to the NRC Operations Center.

(1) The declaration of any of the emergency classes specified in the approved Fort Calhoun Station Emergency Response Plan.

3/ This tabulation supplements the requirements of 5 20.407 of 10 CFR Part 20.

Amendment No. )I, pd, 35 5-12 j

5.9.2- Continued NOTE: Notification for these events shall be made after state or local agencies have been notified but, in all cases, within one (1) hour of the event.

(2)** ' The initiation of any plant shutdown required by the plant's Technical Specifications.

NOTE: The LER required for this event must be submitted 30 days after completion of this shutdown [5 5.9.2(d)]. If the problem which initiated the shutdown was resolved before the shutdown was completed, a 30-day LER is not required.

(3)** Any deviation from the plant's Technical Specifications authorized pursuant to 10 CFR 50.54(x).

(4)** Any event or condition during operation that results in the condition of the nuclear power plant, including its principal safety bar-riers, being seriously degraded; or results in the nuclear power plant being:

(i) In an unanalyzed condition that significantly compromises plant safety; (ii) In a condition that is outside the design basis of the plant; or (iii) In a condition not covered by the plant's operating and emergency pro-cedures.

NOTE: In the event of a Safety Limit Vio-lation, plant operation shall not be resumed without prior Commission approval.

(5)** Any natural phenomenon or other external con-dition that poses an actual threat to the safety of the nuclear power plant or signifi-cantly hampers site personnel in the per-formance of duties necessary for the safe operation of the plant.

(6) Any event that results or should have result-ed in Emergency Core Cooling System (ECCS) discharge into the reactor coolant system as a result of a valid signal.

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5.9.2 -Continued (7) Any event that results in a major loss of emergency assessment capability, offsite re-spcuse capability, or communications capabi-lity (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).

(8)** .Any event that poses an actual threat to the safety of th,e nuclear power plant or signifi-cantly hampers site personnel in the per-formance of duties necessary for the safe operation of the nuclear power plant includ-ing fires, toxic gas releases, or radioactive releases.

(9)** A loss or theft of licensed material in such quantities and under such circumstances thatto it appears a substantial hazard may result persons in unrestricted areas.

(10)** Any event involving byproduct, source, or special nuclear material that may have caused or threatens to cause:

(i) Exposure of the whole body of any in-dividual to 25 rems or more of radi-ation; exposure of the skin of the whole booy of any individual of 150 rems or more of radiation; or expo-sure of the feet, ankles, hands or forearms of any individual to 375 rems or more of radiation; or (ii) The release of radioactive material in concentrations which, if averaged l over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would ex-ceed 5,000 times the limits speci-fied for such materials in Appendix B, Table II, of 10 CFR Part 20; or (iii) A loss of one working week or more I

of facilities operation; or (iv) Damage to property in excess of

$200,000.

' b. Four (4) Hour Notification Following Non-Emergency i

Events I

If not reported under 5 5.9.2(a) of these Technical Specifications, notification to the NRC shall be made as soon as practical and, in all cases, within four (4) hours of the discovery of the occurrence of any of the following events: .

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5.9.2 Continued NOTE: The method of NRC notification shall be the same as that required for one (1) hour notification in 55.9.2(a).

(1)** Any event,-found while the reactor is shut-down, that, had it been found while the re-actor was in operation, would have resulted in the nuclear power plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that significantly compromises plant safety.

(2)** Any event or condition that results in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS). However, actuation of an ESF, including the RPS, that results from and is part of the preplanned sequence during testing or reactor operation need not be reported.

(3)** Any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to:

(i) Shutdown the reactor and maintain it in a safe shutdown condition, (ii) Remove residual heat, (iii) Control the release of radioactive material, or (iv) Mitigate the consequences of an ac-cident.

(4)** Any. airborne radioactive release that exceeds 2 times the applicable concentrations of the limits specified in Appendix B, Table II, of 10 CFR Part 20 in unrestricted areas, when averaged over a time period of one hour.

(5)** Any liquid effluent release that exceeds 2 times the limiting combined Maximum Per-missible Concentration (MPC) listed in 10 CFR Part 20 at the point of entry into the re-ceiving water (i.e., unrestricted area) for all radionuclides except tritium and dis-solved noble gases, when averaged over a time period of one hour.

(6) Any event requiring the transport of a radio-actively contaminated person to an offsite medical facility for treatment.

5-14a

continued 5.9.2 (7) Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an onsite fatality or inadvertent release of radio-actively contaminated materials but shall not include non-radiological effluent releases to the environment.

c. Twenty-Four (24) Hour Notification Following Radio-logical Events Notification to the NRC shall be made, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of the event, of any event in-volving licensed material possessed by the licensee that may have caused or threatens to cause one or more of the following:

NOTE: The method of NRC notification shall be the same as that required for one (1) hour notification in 5 5.9.2(a).

(1)** Exposure of the whole body of any individual to 5 rems or more of radiation; exposure of the skin of the whole body of any individual to 30 rems or more of radiation; or exposure of the feet, ankles, hands or forearms to 75 rems or more of radiation.

(2)** The release of radioactive material in con-centrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 times the limits specified for such materials in Ap-pendix B, Table II, of 10 CFR Part 20.

(3)** A loss of one day or more of the operation of any facilities affected.

(4)** Damage to property in excess of $2,000.

d. Thirty (30) Day Written Reports (LER's)

A Licensee Event Report (LER) shall be submitted to the NRC, within 30 day after the discovery of the event, for any of the following:

(1) Any Reportable Occurrence previously listed in these Technical Specifications requiring a 1, 4, or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> NRC notification that is de-noted by a **.

(2) Any operation or condition prohibited by the Technical Specifications Limiting Conditions for Operation (LCO).

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r 5.9.2 Continued (3) Any event where a single cause or condition caused at least one independent train or chan-nel to become inoperable in multinle systems or two independent trains or channels to be-come inoperable in a single system designed to:

(i) Shutdown the reactor and maintain it in a safe shutdown condition; (ii) Remove residual heat; (iii) Control to release of radioactive material; or (iv) Mitigate the consequences of an ac-cident.

(4) Each exposure of an individual to radiation in excess of the applicable limits in 10 CFR 20.101 or 10 CFR 20.104(a) or these Technical Specifications.

(5) Each exposure of an individual to radioactive material in excess of the applicable limits in 10 CPR 20.103(a)(1), 10 CFR 20.103(a)(2),

or 10 CFR 20.104(b), of these Technical Speci-fications.

(6) Levels of radiation or concentrations of radioactive material in a restricted area in excess of any other applicable limit in these Technical Specifications.

(7) Levels of radiation or concentrations of rad.oactive material (whether or not in-volving excessive exposure of any individual) in an unrestricted area in excess of ten times any applicable limit set forth in 10 CFR Part 20, or in these Technical Specifi-cations.

(8) Any level of radiation or release of radio-active material in excess of limits specified by 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Oper-ations," or in excess of license conditions related to compliance with 40 CFR Part 190.

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JUSTIFICATION, DISCCSSION, AND SIGNIFICANT HAZARDS CONSIDERATIONS The Fort Calhoun Station Technical Specifications are being -

changed to reflect changes to plant organization and to Title 10 CFR concerning shift manning requirements, Significant Event re-porting, and Licensee Event reporting. With the exception of the change to'the shift manning requirements, all changes are purely administrative in nature.

The change to the shift manning requirements involves a change to the number of licensed operators on shift. In the proposed speci-fication, the number of Senior Reactor Operators (SRO) required on site (in addition to the two Reactor Operators required) is two.

The proposed specification also requires one of these SROs to be in the control room at all times. This change is consistent with 10 CFR 50.54 which delineates shift manning requirements.

The plant organizational structure is being changed to reflect re-assignment of_the Quality Control (QC) Department to the Technical

-Department to allow QC a higher level of independence from the Maintenance Department.

The remainder of the proposed changes involve updating reporting requirements to adhere to the new rules on Significant Event and Licensee Event reporting. The proposed Technical Specifications describe events which have one hour, four hour, twenty-four hour, and thirty day reporting requirements in a manner which is con-sistent with the new rules.

Significant Hazards Considerations:

1. This proposed amendment will not involve a significant in-crease in the probability or consequences of an accident previously evaluated. The proposed changes concerning Licensee Event and Significant Event reporting and the plant organizational change are administrative in nature and do not affect the surveillance or operability of any system which functions to prevent or mitigate the consequences of a previously analyzed accident. The proposed change to the shift manning requirements only affects the plant by re-quiring additional expertise in the control room. It does not change the surveillance or operability requirement of any system which functions to prevent or mitigate the con-sequences of a previously evaluated accident.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any accident pre- l viously evaluated. The proposed changes to the reporting <

requirements and plant organization are administrative in nature and the proposed changes to the shift manning require-

' ments do not decrease the availability of on shift oper-ational expertise. None of the proposed changes affect the design or surveillance and operability requirements of the plant systems.

ATTACHMENT B

3. The proposed amendment does not involve a significant re-duction in a margin of safety. The proposed change regard-ing shift manning requirements does not decrease the avail-ability of on shif t operational expertise arid does not af-feet any other design, surveillance, or operability require- The ments which would have-an effect on safety margins.

remaining. proposed changes are administrative in nature and do not affect any design, surveillance, or operability re-quirements which would have an ef fect on safety margins.

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JUSTIFICATION FOR FEE CLASSIPICATION The~ proposed amendment is deemed to be Class II, within the mean-ing of 10 CFR-170.22. It is administrative in nature, has no involve a signi-safety or environmental significance, and does not ficant hazards consideration.

9 ATTACFJiENT C m._ _