LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents

Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents

ML20134N853
Person / Time
Site:	Fort Calhoun
Issue date:	11/20/1996
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20134N840	List: LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20134N836 ML20134N849
References
LIC-96-0183, LIC-96-183, NUDOCS 9611270134
Download: ML20134N853 (16)

Text

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U.S. Nuclear Regulatory Comission LIC-96-0183 j

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ATTACHMENT A i

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9611270134 961120' POR ADOCK 05000285

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D.

Scent Fuel P001 M0di'ication Y

-#s' The licen:ce 1 authori:cd t =0dify the Opent fuel p001 ::

described in the application d ted Occc:bcr 7,1992, ::

supplemented by letter; dated March 10, April 28, and May 14, 1993.

The 00dification : hall consist Of rc=0Ving the existing rack; which have

terage capacity Of 729 fuel :::c=blic: :nd in:crting new rack: "hich will have : stcrage :-apacity Of 1083

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fuel

c=blics.

Therc shall bc 11 frec standing r ck 20dule n

i a discrete-:cnc, t:0 region :terage sy: tem.

The Appendix A Technical Specificat10n: ch:11 he effective :

feMews+

Change; tc Specification: 2.S(10) through (12),

.i.2, and 5.10.3 and Figure 210, Table 3 5, and the b :i; for Specification 2.8 chall be effective when the last new rack 40 installc4r q

(

DE.

License Term The license amendment is contingent on the limitations of monitoring of the long term load factor to assure 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 value of the RTm will not exceed the screening criterion monitoring program being in place.

EF.

Fire Protection Proaram Omaha Public Power District shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the 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 Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

4.

This amended license is effective as of the date of issuance and shall i

expire at midnight on August 9, 2013.

FOR THE ATOMIC ENERGY COMMISSION Original signed by:

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

Enclosures:

1 Appendices A and B - Technical 1

Specifications Date of Issuance: August 9, 1973 Amendment No. MG, MB, MG

c.-

TABl.E OF CONTENTS (Continued)

.P.*ag 4.3 Nuclear Steam Supply System (NSSS).....

4-3 4.3.1 Reactor Coolant System...............

4-3 4.3.2 Reactor Core and Control...........

4-3 4.3.3 Emergency Core Cooling 4-3 4.4 Fuel Storage......................

4-4 4.4.1 New Fuel Storege......

4-4 I

4-4 4.4.2 Spent Fuel Stcrage 4.5 Seismic Design for Class I Systems 4-5 5-1 5.0 ADMINISTRATIVE CONTROLS.

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5.1 Responsibility......

5-1 5.2 Organization

.........................5-1 5.3 Facility Staff Qualifications 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 4

5.6 Reportable Event Action.

5-9 5.7 Safety Limit Violation........

5-9 5.8 Procedures...........

5-9 5.9 Reporting Requirements 5-10 5.9.1 Routine Reports........

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 5-17a 5.10 Records Retention........

5-18 f

5.11 Radiation Protection Program..

5-19 5.12 DELETED 5.13 Secondary Water Chemisty.............

5-20 5.14 Systems integrity................

5-21 5.15 Post-Accident Radiological Sampling and Monitoring 5-21 5.16 Radiological Effluents and Environmental Monitoring Programs.............

5-22 5.16.1 Radioactive Effluent Controls Program....

5-22 I

5.16.2 Radiological Environmental Monitoring Program........

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 L' ': e ":=: - C n!=: ""mp Op=::::

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6.2 DELETED Un of : Sp -' F :! Ship;ing C d

'I 6.3 DELETED A=:!!: y F:5:!:- Artem :!: ? ::!::!^n S:tpe'-

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6.4 DELETED Op =:!c ""'S L = "n.= 75" c'! ec= D:: rte-S:f ag: Opr hk 51 l

lii Amendment No. 32,?1,A3.51,55,57, i

"F1,On, Of, On,n1,no.1 A 1.

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TABLE 2-3 a.

Instrument Operating lieauirements for Engineered Safety Features

Test, Maintenance Minimum Minimum Permissible and Operable.

Degree of Bypass Inoperable Functional Unit Channels Redundancy Condition Bynass 1

Safety iniection A

Manual 1

None None N/A B

liigh Containment Pressure A 2""d) 1 During Leak (0

B 24**d) 1 Test C

Pressurizer Low / Low Pressure A 2"d) 1 Reactor Coolant (0

B 2""d >

1 Pressure Less nan 1700 psia *>

2-Containment SnraY A

Manual i

None None N/A B

liigh Containment Pressure A 2""'"d) i During Leak (0

B 2""'"d) 1 Test

__ Pressuripthow/ Low C

7 Preisiire A 2*"'"d) 1 Reactor Coolant (O

B 2""'"d) 1 Pressure Less M

nan 1700 psia *)

3 Recirculation A

Manual 1

None None N/A B

SIRW Tank Low Level A 2"""

I None (j)

B 2"""

1 4

Emercency oft-Site Power Trin A

Manual 1")

None None N/A B

Emergency Bus Low Voltage (Each Bus)

-Loss of Voltage 2'd) 1 Reactor Coolant (0

-Degraded Voltage 2*"d) 1 Temperature Less Than 300"F 2-68

. Amendment No. 41,64,88 M

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TABLE 2-4 1

l INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS I

Test, l

Maintenance Minimum Minimum Permissible and j

Operable Degree of Bypass Inoperable j

h f_unctional Unit Channels Redundancy Condition BVDa59

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Manual 1

None None N/A j

B Containment liigh Pressure A

2""*)

1 During Leak (0

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B 2"X')

1 Test i

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2*"*)

1 Reactor Coolant (O

B 2""4 1

Pressure Less Than

"~ Pressure 1700 psia *)

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2 Steam Generator Isolation P

A Manual 1

None None N/A l

i B

Steam Generator j

Isolation 1

None None N/A I

(i) Steam Generator Low Pressure A 2/ Steam 1/ Steam Steam Generator (0

Gen ")

Gen Pressure Less Than l

600 psia")

B 2/ Steam 1/ Steam i

Gen ")

Gen l

(ii) Containment liigh Pressure A

2""4 1

During Leak (0

B 2*"d i

Test 3

Ventilation isolation A

Manual 1

None None N/A j

l B

Containment Iligh i

Radiation A

1(d)

None If Containment (0

B l'd)

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. 88,a?,!O8,'52,!52,173

G 5.0 ADMINISTRATIVE CONTROLS 5.2 Oreanization (Continued) b.

An Operator or Technician qualified in Radiation Protection Procedures shall be onsite when fuel is in the reactor.

I 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 operation.

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Fire protection program responsibilities are assigned to those positions and/or groups designated by asterisks in USAR 12.1-1 through 12.14 according to the procedures specified in Section 5.8 of the Technical.Sp'ecifications.

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Thism6sst'6f'5WitiinsM6rksdIbyllinit stiffinsmbiiipeifoimininfeth e.

related fuixsionnhall bilirnitsdf and bontrolled'in"accordanceMith the NRC

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The Supervisor - Operations, the Shift Supervisors and Licensed Senior Operators shall hold a senior reactor operator license. The Licensed Operators shall hold a reactor operator license.

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1 5-la Amendment No. 38,54,85,115, M~^

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5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Oualification 5.3.1 Each member of theylant staffshall meepeexceed theminimum-qualificati5its'of NSI~NE1971 for comp!Irable p6sitions, witiithe' exception of the Supervisor h Radiatica Pro: c:ica (SPS) ManageURadiationW6ikiion (MRP) and thWShif

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Tedi cal ~ATvis'oP(STA(d= Eptinib7r~1975$ntitled " Personnel Regulatory GuipTdate The SRP MRP is onsidered to meet the educational and experience Training"((ns set,gReghlatory Guide 1.8 with at least five years qualificati in applied r'adnation protection and extensive fonn7ala{'ning in radiation protection. The Shift Technical Advisor shall have a bac lor ls egree or equivalent in a scientific or engineering discipline with spec raim g in plant design and response and analysis of the plant for transients and acci nts. l 1 i 1 5-lb Amendment No. 445

) o 5.0 ' ADMINISTRATIVE CONTROLS. t 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. [ t c. Provide immediate written notification to the Division Manager - Nuclear i Operations and the Safety Audit and Review Committee of disagreement between the Plant Review Committee and the Manager - Fort Calhoun { Station; however, the Manager - 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 Division Manager - Nuclear Operations and Chairperson of the Safety Audit and Review Committee. f t 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 l e. instrumentation and control f. radiological safety g. mechanical and electrical engineering h. quality assurance I. fire protection Composition i 5.5.2.2 The Safety Audit and Review Committee shall be composed of. C I Chairperso : Senior Vice Presiden: Memliefa5lspp6i.nted bfithEVid Member: ide Member: DTvision Manager - Nuclear Services l Member: Division Manager - Nuclear Operations j Member: Division Manager - Production Engmeermg Member: Manager - Fort Calhoun Station 1 -Member: Other qualified OPPD personnel and/or consultants as required and as determined by the SARC Chairperson i 5-5 Amendment No. 9,19,60,76,84,93,"), j 101,115,119,132,141,119,157,160,168

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• Q ADMINISTRATIVE CONTROLS 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. i b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety. l 1 c. Licensee Event Reports (LER). d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications. e. Records of reactor tests and experiments. Records of chan i gw.__ ges made to Operating Procedures, f. ~ i g. Secri of radicactive tipment:. DELETEDl v ~ h. Records of annual physical inventory of all source material of record. j i I l f t 5-18 Amendment No. 7h99

, 5.0 ' ADMINISTRATIVE CONTROLS l 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 experiments pursuant to 10 CFR 50.59. k. Records 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 JRecoids'bf radi6 active shipnientsj(s Control Program, leulation-Manualand-tirProce j \\ p. wms/ ~ 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 Technical Specifications 2.8 and 4.4). 5.11 Radiation Protection Procram Procedures for personnel radiation protection shall be prepared consistent with j the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. I 5-19 Order 70/24/S0 Amendment No. 59d4,93,99,105,152,155,175

~ 5.0 ' ADMINISTRATIVE CONTROLS 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 6 20.1601(c), each high ~ radiation area (as defined in f 20.1601) 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 radiatien monitoring device which continuously indicates the radiation dose rate in the area, b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring devji em.rg made after the dose rate level in the area has been established eef snd personnel have been made knowledgeable of them. \\C 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 gerform periodiuadiMion survedirnTiilt thA requency specified by tfie Supervi';c Radiation Pro! ction pimige19 Radiati6n'Protectidn]MRP) in the Radiation Work Permit. A A-n N-5.11.2 The requirements of 511, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hi** but less than 500 rads /hr*** (Restricted Ifigh Radiation Area). In add'. tion, locked doors shall be provided to prevent unauthorized entry into suen areas and the keys shall be maintained underaheadministrative_ control opneJhhq Supervisor on duty and/orge Supervi;cr Radiatica Protectia MRP with the j / following exception: ( u a. In lieu of the above, for accessible localized Restri:ted Iligh Radiation Areas located in large areas such as containment, where no lockable enclosure exists in the immediate vicinity to control access to the Restricted High Radiation Area and no such enciasure 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, il conspicuously posted, and j iii a fit.shing 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 raniation areas.
  • At 30 centimeters (12 inches) from the radiation source or from any surface penetrated by the radiation.

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

5-19a Amendment No. 28,61,132,154

\\ U.S. Nuclear Regulatory Commission LIC-96-0183 ATTACHMENT B l l l

DISCUSSION, JUSTIFICAT10N AND NO SIGNIFICANT HAZARDS CONSIDERATIONS DISCUSSION AND JUSTIFICATION: Omaha Public Power District (OPPD), the licensee for Fort Calhoun Station (FCS), Unit No.1, proposes to amend Operating License No. DPR-40 and the Technical Specifications (TS) contained in Appendix A therein as follows: ParaaraDh 3.0. SDent Fuel Pool Modification Paragraph 3.D of Facility Operating License No. DPR-40, is proposed for deletion (Paragraphs 3.E and 3.F will be renumbered to 3.D and 3.E ( respectively). Paragraph 3.D describes the modification that increased the spent fuel pool storage capacity and states that the applicable Specifications will be effective when the last new rack is installed. As stated in OPPD's i letter to the NRC dated August 12, 1994 (LIC-94-0167), the last new storage rack was installed on August 8, 1994. Since the applicable Specifications have been effective since then, the current Paragraph 3.0 is no longer necessary. Therefore, Paragraph 3.D should be removed from the License and Paragraphs 3.E and 3.F renumbered to 3.D and 3.E respectively. Technical SDecifications. Table of Contents Table of Contents, Section 6.0, " Interim Special Technical Specifications," Subsections 6.1 through 6.4 are proposed for deletion. As shown on page 6-1 of the FCS Unit No.1 Technical Specifications, all of the interim specifications have been deleted by previous Amendments. Therefore, this proposed revision will update the Table of Contents accordingly. TS 2.15. Tables 2-3 & 2-4 Item 2C of Table 2-3 and Item IC of Table 2-4 currently list the description of the Functional Unit as " Pressurizer Low / Low." 0 PPD proposes to correct the description to the proper terminology which is " Pressurizer Low / Low Pressure." TS 5.2. Oraanization Technical Specification 5.2, Item e, provides limitations on the work hours of plant personnel performing safety related functions. In lieu of the current guidance contained in Item e, OPPD proposes to control the amount of overtime J worked by these personnel in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12). Therefore, the current guidance in TS 5.2, Item e, is proposed for replacement by a statement committing to control overtime in accordance with GL 82-12. This option is in accordance with NUREG-1432, Standard TS for Combustion Engineering Plants, Specification 5.2.2e. 1 1 J

.. ~. DISCUSSION AND JUSTIFICATION (CONTINUED): TS 5.5. Composition of the Safety Audit and Review Committee Technical Specification 5.5.2.2 states the composition of the Safety Audit and Review Committee and states that the Chairperson is the Senior Vice President. It is proposed that the specific title of the Chairperson be deleted and replaced with " Member as appointed by the Vice President." This will allow the flexibility to change chairmanship of the committee amongst the members. j i TS 5.3. Facility Staff Qualification TS 5.11. Radiation Protection Procram l During a recent reorganization of OPPD's Nuclear Operations Division, the position of Supervisor - Radiation Protection was upgraded to Manager - t Radiation Protection. As a result, TS 5.3.1 and 5.11 references to " Supervisor - Radiation Protection" must be changed to " Manager - Radiation Protection." In addition, an editorial change to add an apostrophe to " bachelor's" degree for TS 5.3.1, and a typographical correction to revise the 1 word "end" to "and" contained in TS 5.11.1 are proposed. TS 5.10 Record Retention ~ Technical Specification 5.10 must be revised to comply with recent changes to 10 CFR 20 that require records of radioactive shipments to be retained until license termination. Therefore, OPPD proposes to remove the requirement from p TS 5.10.1g (5 year retention) and place !t in TS 5.10.2 (duration of the i Facility Operating License retention). OPPh is in compliance with the requirements of 10 CFR 20 as applicable FCS procedures list the correct retention period for radiation protection documentation. The Section 5.0 title is. inserted at the top of page 5-18 from which it is currently missing. Thus, these are administrative changes designed to update the FCS Unit No. 1 TS to reflect current regulatory and procedural requirements and correct a minor format discrepancy. s 2

..r. 1 BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATIONS: The proposed Technical Specification (TS) changes do not involve significant hazards considerations because operation of Fort Calhoun Station (FCS) Unit No.1 in accordance with these changes would not: (1) Involve a significant increase in the probability or consequences of an i accident previously evaluated. The changes requested are administrative in nature. Paragraph 3.0 was t placed in the License by Amendment No.155 to authorize Omaha Public Power District (0 PPD) to increase the storage capacity of the FCS spent fuel pool. Amendment No. 155 stated that the TS as issued would be i effective when the last new rack was installed. Since the last new rack was installed on August 8, 1994, Paragraph 3.D is no longer necessary and should be deleted from the License. c Table of Contents, Section 6.0, " Interim Special Technical Spedfications," Subsections 6.1 through 6.4 are proposed for deletion i becaae all of the Specifications referred to have been deleted by previcus Amendments. The revision proposed for TS 2.15 (Item 2C of Table 2-3 & Item 1C of Table 2-4) will insert the correct terminology (Pressurizer Low / Low Pressure) into the Functional Unit description. The revision proposed for TS 5.2 will require the control of overtime worked by personnel to be in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12) in lieu of stating the specific times requirements from the Policy as the current TS does. This option is in accordance with NUREG-1432, Standard TS for Combustion Engineering Plants, Specification 5.2.2e, and will allow work groups to be on twelve hour shifts. The revision proposed for TS 5.5.2.2 will replace the specific title of the Chairperson of the Safety Audit and Review Committee and replace it with " Member as appointed by the Vice President." This will allow the flexibility to change chairmanship of the committee amongst the members. ) The. revision to TS 5.10 concerning retention of records of radioactive shipments will update the TS to current 10 CFR 20 requirements. Plant procedures already comply with current 10 CFR 20 record retention requirements. The addition of the Section 5.0 title corrects a minor format discrepancy. 3

i s BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATIONS (CONTINUED): These proposed revisions are administrative in nature. The proposed revisions have no effect on any initial assumptions-or operating restrictions assumed in any accident, nor do these changes have any effect on equipment required to mitigate the consequences of an accident. Therefore the proposed revisions do not involve a significant increase in the probability or consequences of an accident previously evaluated. (2) Create the possibility of a new or different kind of accident from any -accident previously evaluated. The proposed revisions correct minor errors, remove outdated .information, are consistent with changes in organizational structure, 10 CFR Part 20, or NUREG-1432, " Combustion Engineering Standard Technical l Specifications (STS). These changes will not result in any physical alterations to the plant configuration, changes to setpoint values, or changes to the application of setpoints or limits. No new operating modes are proposed as a result of these changes. Therefore the proposed changes do not create the possibility of a new or different kind of i accident from any accident previously evaluated. (3) Involve a significant reduction in a margin of safety. The revisions listed above correct minor errors, remove outdated information, or are consistent with changes in organizational structure, i 10 CFR Part 20, or Standard TS. These changes will not result in any physical alterations to the plant configuration, changes to setpoint values, or changes to the application of setpoints or limits. Therefore i the proposed changes do not involve a significant reduction in a margin of safety. Based on the above considerations, it is OPPD's position that this proposed amendment does not involve significant hazards considerations as defined by 10 CFR 50.92. The proposed changes will not result in a condition that significantly alters the impact of the Station on the environment. Thus, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9), and pursuant to 10 CFR 51.22(b) no environmental assessment need be prepared. 4 ,}}