ML20203M412

Amend 184 to License DPR-40,revising TS to Reflect Administrative Changes

ML20203M412
Person / Time
Site:	Fort Calhoun
Issue date:	02/03/1998
From:	Wharton L NRC (Affiliation Not Assigned)
To:
Shared Package
ML20203M399	List: ML20203M396 ML20203M412 ML20203M416
References
NUDOCS 9803060380
Download: ML20203M412 (15)

Text

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p< *, UNITED wTATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30606-0001 4,

OMAHA PUBLIC POWER DISTRICT DOCKET NO 50-285 FORT CALHOUN STATION. UNIT NO 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.184 License No. DPR 40

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amenoment by the Omaha Public Power District (the licensee) dated November 20. 1996, and supplemented by letter dated February 20. 1997, and submittal dated March 25, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1:

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: (1) that the activities authorized by this amendment _can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:

D. The issuance of this license 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 CFP Dart 51 of-the Commission's regulations and all applicable rea,,rements have been satisfied.

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2.

Accordingly., Facility Operating License No. DPR 40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical SDecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 184 are hereby incorporated in the license. The licensee shall operate the facility in ac crdance with the bchnical Specifications.

In addition, the license is a ended to delete par graph 3.D to FacilTty Operating License No. DPR 40 3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/

L. Raynard Wharton. Project Manager Project Directorate IV-2 Division of Reactor Projects - III/IV l Office of Nuclear Reactor Regulation Attachments: Changes to the Technical Specifications Date of Issuance: February 3, 1998 I

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• Pages 4 and 4a are attached, for convenience, for the composite license to reflect this change.

4-A, Maximum Power Level Omaha Public Power District is authorized to operate the Fort Calhoun Station. Unit 1. at steady state reactor core power levels not to exceed 1500 megawatts thermal (rated power).

B. Technical SDecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. . are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

C. Security and Safeauards Continoency Plans The licensee shall fully 1mplement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90

. and 10 CFR 50.5d(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21. are entitled: " Fort Calhoun Station Physical Security Plan," with revisions submitted through September ? , 1988: " Fort Calhoun Station Guard Training and Qualification Plan," with revisions submitted through August 17, 1979: and Fort Calhoun Station Safeguards Contingency Plan," with revisions submitted through March 20, 1979. If certain security modifications are delayed beyond expectations of the schedule, approved compensatory measures must be implemented during the transition period.

I D. License Term l

The license amendment is contingent on the limitations of monitoring of the long-term load factor to assure that it does not exceed the assumed value of 0.77, and that a reevaluation of the end of license fluence with ENDF/B-VI cross sections and updated uncertainties will be performed to assure that the 'alue of the RT ns will not exceed the screening criterion monitor ~ng program being in place.

Amendment No. ML1.184

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E. fire Protection Proaram j Omaha Public Power District shall implement and maintain in effect all 3rovisions of the approved Fire Protection Program as described in t1e Updated Safety Analysis Report for the facility and as approved in the SERs dated February 14. and August 23. 1978.

November 17. 1980. April 8. and August 12. 1982. July 3. and November 5. 1985. July 1. 1986. December 20. 1988. November 14 1990. March 17. 1993, and January 14. 1994, subject to the following provision:

Omaha Public Power District may make changes to the approved Fire Protection Program without prior approval of the .c Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. Additicaal Conditions The Additional Conditions contained in Appendix B. as revised through Amendment No. 181, are hereby incorporated into this license. Omaha Public Power District shall operate tne facility in accordance with the Additional Conditions.

4.

This amended license is effective as of the date of issuance and shall expire at midnight on August 9. 2013.

FOR THE NUCLEAR REGULATORY C0liMISSION Original signed by:

A. Giambusso A. Giambusso. Deputy Director for Reactor Projects Directorate of Licensing

Enclosures:

1. Appendix A - Technical Specifications

2. Appendix B -

Additional Conditions Date of Issuance: August 9. 1973 Amendment No. 155.158.1E 0.181,184

, ATTACHMENT TO LICENSE AMENDMENT NO. 184 FACillTY OPERATING LICENSE NO. OPR-40 DOCKET NO. 50 285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of char.ge.

REMOVE INSERT iii ii' 2-68 2 68 2 69 2 69 5-lb 5-lb

' 5-4 5-4 5-5 5-5 59 5-9 5-18 5-18 5-19 5-19 5-19a 5-19a h

W ---

TABl.E OF CONTENTS (Continued) fags 4.3 Nuclear Steam Supply System (NSSS) . . . . .

, ....... .... .. ... . . 4-3 4.3.1 Reactor Coolant System . . . . . . . . ......... . . . . . . . . . . . . .. . . 4-3 4.3.2 Reactor Core and Control . . . . . . . . . . . . . . . .

' ..., ..... ... . 43 4.3.3 Emergency Core Cooling . . ... ........ . ..... . . ..... 4-3 4.4 Fuel Storage .....,... ......... ..... .......... .. . . . 4-4 4.4. t New Fuel Storage . . . .................................. .4-4 4.4.2 Spent Fuel Storage . . . . . . . . . . . ....... .............. . 4-4 4.5 Seismic Design for Class I Systems ..... .................. . . ...... 4-5 L 5,0 AININISTRATIVE CONTROLS , .... . . .. .. . .. . . . 1 5.1 Responsibility . .... .. .... ., , ... ... . .. .51 5.2 Organization .. . ..... ..... ...... . .. ..... . . 5-1 5.3 Facility Staff Qualifi,ations .. . . . .... ...... ...... .. 5-la 5.4 Training . . . . . . .... . ............. .... .......... .5-3 5.5 Review and Audit .. ..... ......... .. . . ............ .. . 5-3 5.5.1 Plant Review Committee (PRC) ... ... . .. . , . . ... . 5-3 5.5.2 Safety Audit and Review Committee (SARC) . . . .. . .. , ,. .... ...... 5-5 5.6 Reponable Event Action . . . . . . . . . . . ....... .... .. .......59 5.7 Safety Limit Violation ....... ....... ........ ... ......... . 5-9 5.8 Procedures . ............. ... .. . .......... . . . . .. .. . 5-9 5.9 Reporting Requirements ..... ................ ......... ..... . 5 10 5.9.1 Routine Repons ...... ... ...... .. . ......... . .5-10 5.9.2 Reportable Events . .. . ...... . . ....... . . 5-12 5.9.3 Special Reports ... . . . . ... .. . . . . . . . 5 15 5.9.4 Unique Reporting Requirements . ... ..........., . . . . . . 5 15 5.9.5 Core Operating Limits Report .. . . .. . .. ... .... . 517a 5.10 Records Retention . . . . . . . . ... .. . . .... . . ..... .. . 5 18 5.11 Radiation Protection Program . . . ... ......... ... .. .. .. .... 5-19 5.12 OELETED 5.13 Secondary Water Chemistry ..... .. .... ... .. ........... .. . 5 20 5.14 Systems integrity . . . . . . . . . . . . ............. . . .. .. . . . . 5-21 5.15 Post-Accident Radiological Sampling and Monitoring ....... . . .... .... 5-21 5.16 Radiological Effluents and linvironmental Monitoring Progranu . . . . . . . . . . ... 5-22 5.!5.1 Radioactive Eftluent Controls Program ..... . . .. . . . 5-22 5.16.2 ~ Radiological Enviror. mental Monitoring Progr.m . . ... . .. .. 5-23 5.17 Offsite Dose Calculation Manual (ODCM) . ,,. .. . . .. .. . 5-25 5.18 Process Control Program (PCP) ... .,, .. .. . .. .... 5-26 6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS . . . ..... ... . 6-1 6.1 DELETED 6.2 DELETED 6.3 DELETED 6.4 DELETED iii Amendment No. 32,3! 13,51,55,57, 73,90,86,89,93, " ,' " ,!52,!57,184 j

4 TAB 112 3 instrument Operatina Keouirements for Enmineered Safety Featurn Test, Staintenance Slinimum Sfinimum Permissible and Operable Degree of By pass Inoperable

& Eynctional linit Q!annels Redundanc5 Condition Bt pass 1 Safety Iniection A hianual i None None N/A Il liigh Containment Pressure A 2'"d' 1 During Leak (0 B 2'"* 1 Test C Pressurizer Low /lmw Pressure A 2'*"* 1 Reactor Coolant (0 B 2'"* 1 Pressure less Than 1700 psia *'

2 Containment Snrav A hlaaual 1 None None N/A i

4-Il liigh Containment ..

Pressure A 2'""* 1 During Leak (0 B 2'"'"* 1 Test C Pressurizer Low / Low-

., Pressure A 2'""* 1 Reactor Coolant (0

] B 2' *""* 1 Pressure Less l

Than 1700 psia *'

3 Recirculation

-A hianual i None None N/A

-B SIRW Tank low Level A 2'"" i None (j)

B 2'"" 1 4 Emercency Off-Site Power Trin A hianual l '* None ' None N/A B Emergency Bus Low Voltage (Each Bus)

Loss of Voltage 2'* 1 Reactor Coolant (0

-Degraded Voltage 2'"* 1 Temperature Less han 300*F 2-68 Amendment No. d ',65 ,'73184

TAILLE 24 1

INSTRtrMENT OPERATING CONDITIONS FOR ISOI.ATION FI'NCTIONS Test.

Maintenance Minimum Minimum Permissible and Operable Degree of Bypass inoperah'e

& Functional l' nit Channels Redundanes Condition Bypass

! Containment isolac in A Manual 1 None None N/A 11 Containment fligh Pressure A 2'"" 1 During Leak (0 B 2' "" 1 Test C Pressuriter low! Low A 2' "" 1 Reactor Coolant (O Pressure B 2" 1 Pressure Less Than 1700 psia""

l 2 Steam Generator Isolation A Manual i None None N/A

-V: B Steam Generator Isolation 1 None None N/A (i) Steam Generator low Pressure A 2/ Steam 1/ Steam Steam Generator (O Gen "' Gen Pressure Less Than 600 psia"'

B 2/ Steam 1/ Steam Gen '" Gen (iin Containment High Pressure A 2'"" i Durmg Leak (0 B 2" 1 Test 3 Ventilation isolation A Manual 1 None None N/A B Containment High Radiation A l '* None If Containment (0 B l '* None Relief and Purge Valves Are Closed a A and B circuits each have 4 channels.

b Auto removal of bypass prior to exceeding 1700 psia.

c Auto removal of bypass prior to exceeding 600 psia.

2-69 Amendment No. ' 93,'O ,!52,! $3,'73, D I

l', 5.0 ADMINISTRATIVE CONTROLS t

5.3 Facility Staff _ Qualification 5.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, with the exception of the Manager -

l Radiation Protection (MRP) and the Shift Technical Advisor (STA). The MRP shall I meet the requirements set forth in Regulatory Guide 1.8 dated September 1975, entitled " Personnel Selection and Training" The MRP is considered to meet the i l-educational and experience qualifications set forth in Regulatory Guide 1.8 with at least five years of experience in applied radiation protection and extensive formal-training in radiation protection. The Shift Technical Advisor shall have a bachelor's g

degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

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k 5-lb Amendment No. Es,184

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5.0 ADMINISTRATIVE CONTROLS r .

Responsibilities l- 5.5.1.6 The Plant Review Committee shall be responsible for:

a. Review of (1) Ac..inistrative' Controls Standing Orders and changes I

thereto, (2) procedures required by Specification 5.8 and requiring a 10 CFR 50.59 safety evaluation, and (3) proposed changes to procedures required by Specification 5.8 and requiring a 10 CFR 50.59 safety evaluation;

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to the Technical Specifications.

d. Review of all proposed changes to the Core Operating Limits Report.

c. Review of all proposed-changes or modifications to plant systems or equipment that affect nuclear safety.

f. Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Vice President and to the Chairperson of the Safety Audit and Review Committee. {

g. Review of facility operations to detect potential safety hazards.

h. Performance of special reviews and investigations and reports thereon as requested by the Chairperson of the Safety Audit and Review Committee,

i. DELETED

j. DELETED

k. Review of the Fire Protection Program Plan and shall submit changes to the Chairperson of the Safety Audit and Review Committee.

1. Review of all Reportable Events.

Aulhgijy 5.5.1.7 The Plant Review Committee shall:

a. Recommend in writing to the Manager - Fort Calhoun Station approval or disapproval of items considered under 5.5.1.6(a) through (e) above.

5-4 Amendment No. 9,19.04."),115,141, 119,157.16^,169,184 i

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5.0 AD.\11NISTRATIVE CONTROLS 5.5.1.7 b. Render determinations in writing with regard to whether or not each item considered under 5.5.1.6(b) through (f) above constitutes an unreviewed safety question.

c.

Provide immediate written notification to the Vice President and the Chairperson of the Safety Audit and Review Committee of disagreement between the Plant Review Committee and the hianager - Fort Calhoun Station; however, the hianager - Fort Calhoun Station shall have responsibility for resolution of such disagreements pursuant to 5.1.1 above.

Records 5.5.1.8 The Plant Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President and Chairperson of the Safety Audit and Review Committee. l 5.5.2 Safety Audit and Review Committee (SARC)

Function 5.5.2.1 The Safety Audit and Review Committee shall function to provide the independent review and audit of designated activities in the areas of:

a. nuclear power plant operation

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance i, fire protection Comoosition 5.5.2.2 The Safety Audit and Review Committee shall be composed of:

Chairperson: hiember as appointed by the Vice President l 3 hiember: Vice President h hiember: Division hianager - Nuclear Assessments hiember: Division hianager - Engineering & Operations Support hiember: hianager - Fort Calhoun Station hiember: Other qualified OPPD personnel and/or consultants as required and as determined by the SARC Chairperson 5-5 Amendment No. %19,50,75,8 t,93,99-401,115,119,132,111,119,157,160,168,184

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I 5.0 M)MINISTRATIVE CONTROL S l ,

5.6 Renonable Event Action f

5.6.1 The following actions shall be taken in the event of a REPORTABLE EVENT:

a. The Commission shall be notified pursuant to the requirements of 10 CFR 50.72, if applicable.

b. Each Reportable Event shall be reviewed by the Plant ko.iew Committee and submitted to the Chairperson of the Safety Audit and Review Committee and the Vice President. I

c. Submit reports of Reportable Events pursuant to the requirements of Specification 5.9.2.

5.7 Safety Limit Violation j

5.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least IlOT SilUTDOWN within I hour,

b. The Safety Limit Violations shall be reported to the Vice President and the l Chairperson of the Safety Audit and Review Committee (SARC) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the Plant Review Committee. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. _ The Safety Limit Violation Report shall be submitted to the Chairperson of the Safety Audit and Review Committee and the Vice President l within 14 days of the violation.

5.8 Procedures -

5.8.1 Written procedures and administrative policies shall be established, implememed -

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.

5.8.2 Each procedure of Specification 5.8.1, and changes thereta, and any other procedure or procedure change that the Manager - Fort Calhoun Station determines to affect nuclear safety, shall be reviewed and approved as described below, prior to implementation.

5-9 Amendment No. 9,19,38,8!.99, 115,119,157,184

5.0 ADMINISTRATIVE CONTROL,S 5.10 Record Retention 5.10.1 The following records shall be retained for at least five years:

a. Records, and logs of facility operation covering time interval at each power level.

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

c. Licensee Event Reports (LER).

d. Records of surveillance activities, inspections and calibrations required by these Tcn: cal Specifications.

c. Records of reactor tests and experiments,

f. Records of changes made to Operating Procedures,

g. DELETED.

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h. Records of annual physical inventory of all source material of record.

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5-18 Amendment No. 75.99,184

9.0 ADMINISTRATIVE CONTROLS 5.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Records of drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

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

c. Records of 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,

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA Manual.

J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and expenments pursuant to 10 CFR 50.59.

k. Reccrds of meetings of the Plant Review Committee and the Safety Audit and Review Committee.

1. Records of Environmental Qualification of Electric Equipment pursuant to 10 CFR 50.49.

m. Records of the service lives of all hydraulic and mechanical snubbers, including the date at which the service life commences and associated installation and maintenance records,

n. Records of analyses required- by the Radiological Environmental Monitoring Program,

o. Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program,

p. Records of radioactive shipments.

l 5.10.3 A complete record of the analysis employed in the selection of any fuel assembly to be placed in Region 2 of the spent fuel racks will be retained as long as that assembly remains in Region 2 (reference Tr .hnical Specifications 2.8 and 4.4).

5.11 Badiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

5-19 Order 70.!24!80 Amendment No. 59.S5,93.99.105,152,155.!?5,184 I

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5.0 ADN1INISTRATIVE CONTROIJ 5.11.1 In lieu of the " control device" required by paragraph 20.1601(a) of 10 CFR Part 20, and as an alternative method allowed under s 20.1601(c), each high radiation area (as defined in i 201601) in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by required issuance of a Radiation Work Permit.

• Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area,

b. A radiation monitoring device which continuously integrates the radiation t

dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been g made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the hianager-Radiation Protection (h1RP) in the Radiation l

Work Permit.

) 5.11.2 The requirements of 5.11.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr" but less than 500 rads /hr*** (Restricted liigh Radiation Area). In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the h1RP with the following exception: l

a. In lieu of the above, for accessible localized Restricted liigh Radiation Areas located in large areas such as containmeat, where no lockable enclosure exists in the immediate vicinity to control access to the Restricted liigh Radiation Area and no such enclosure can be readily constructed, then the Restricted High Radiation Area shall be:

i. roped off such that an individual at the rope boundary is exposed to 1000 mrem /hr or less, ii conspicuously posted, and iii a flashing light shall be activated as a warning device.

• Radiation Protection personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

• • At 30 centimeters (12 inches) from the radiation source or from any surface penetrated by the radiation.

• • • At 1 meter from the radiation source or from any surface penetrated by the radiation.

5-19a Amendment No. 28,61,132,15 t,184

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