ML20091D602

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Proposed Changes to Tech Specs,Adding NRC Std OL Condition for Fire Protection
ML20091D602
Person / Time
Site: Arkansas Nuclear  
Issue date: 10/15/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20091D600 List:
References
NUDOCS 9110250168
Download: ML20091D602 (39)
v • d • e


Text

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i ENCLOSURE 1 PROPOSED ANO-1 OPERATING LICENSE CilANGE 1

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- ~'?11005016E 911015 PDR ADOCK 05000313 P-PDR

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1.

Identification of aiampling schedule for the critical parameters and control points for these parameters:

2.

Identification of the p1ocedures used to measure the values of the critical parameters:

3.

Identification of process sampling points:

4.

Procedures for the recording and management of data; j

S.

Procedures defining corrective actions for off-control point chemistry conditions: and

)

6.-

LA procedure identifying the authority responsible-for the interpretation of the data and the sequence ar.d i

timing of administrativo events required to initiate a corrective action.

(8)_ FIRE-PROTECTION E01 shall implement and maintain in effect all provisions of' the approved Fire Protection Program as described in Amendment-9A to the Safety Analysis Report and as approved In the Safety Evaluation Report dated

.. subject to-the following provision:

The licensee 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.

3.

This license is effective as of~the date of issuance and shall expire at midnight. May 20, 2014.

-FOR THE ATOMIC ENERGY COMMISSION

A. Giambusso.LDeputy' Director for Reactor Projects Directorate of Licensing Attachments-Appendices A and B - Technical

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Specifications

'Date of Issuance.May 21 1974 5

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s ENCI,0SURE 2 PROPOSED ANO-1 TECilNICA1. SI'ECIFICATIOh' CllANGES-5 s

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-3.5.5 l' ire Detection Inst rumenta. tion del.ETED i

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Amendment No. 3 5, A 3, s /, J J r, 53d i

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-SAFETY-RELATED AREAS PROTECTED BY llEAT/SHOKE DETECTORS 1

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Amendment No M 53e

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3.17 Firo Suncression Water Systffn DELETED Amendment-No. $p, 57, JJE 66m

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I 3.18 FIRE SUPI'RESSION SI'l!1NKLER SYSTEM i

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3.19 CONTROL ROOH AND AUXILI ARY CONTROL R00H. flALON SYSTEMS -

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Amendment No. $f, J/, JJF 66o

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- FIRE DETECTION INSTRUMENTATION

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s Tablo 6.2-1 ARKANSAS NUCLEAR ONE l

-li1K11101. jill]FT CREW. COMPOSITION #

ONIT 1 LICENSE COLD AND REFUELING CATEGORY ABOVE COLD SilVTDOWN SilUTDOWNS SOL 2

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1 NON-LICENSED 3

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1 SilIFT TECilNICAL ADVISOR 1

Nonc required

  • Does not include the licensed Senior Reactor Operator or Senior-Reactor Operator Limited to Fuel llandling, supervising refueling operations after the initial iuol loading.

-(/Shif t crow compositi, a may be less than the minimum requirements for a period of timo 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 accommodato unexpected

. absence of on duty. shif t crew members provided immodlate action. is taken to restore the shif t crew composition to within the minimum requirements of Table 6.2-1.

Additional Requirements:

1.

At least onn licensed Operator shall be in the control room when fuel is in the reactor.

2.

At least two licensed Operators shall bo present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

.3.

'An IndivJdual qualified in radiation protection procedures shall be on sito whnu fuel is in thn reactor.

4.

All refueling operations after the initial fuel loading shall be directly supervised by olther a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel llandling who has no other concurrent responsibilities during.this operation.

5.

DELETED Amendment No. Jfi, $$, $5, $$

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h.

Performance of apecial reviews, investigations, or analyset and reports thereon as requested by the Plant Manager, ANO-1, General Msncger, Plant Operations or the Safety Review Committee, i.

Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the General Manager, Plant Operatinns and the Safety Review Committee.

j.

Review of tha Emergency Plan and implementing procedures anl submittal of recommended changes to the General Manager, Pinnt Operatior s and the Safety Review Committee.

k.

Review of changes to the Offsite Dose Calculation Manual and the Process Control Program.

1.

Review of changes to the Fire Protection Program and implementing

_ procedures and submittal of recommended changes to the General Manrger, Plant Operations and Safety Review Committee.

AUTHORITY 6.5.1.7.

The Plant Safety Committee thall:

Recommend in writing their approval or disapproval of items a.

conaldered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(n) through (e) above constitutes an ur. reviewed safety question, Provide written notification within 24 houra to the Vice c.

President, 0,3 rations ANO and the Safety Review Committee of disagreemen* le la the PSC and the Plant Manager, ANO-1 or the General Manager, Plant Opera' ions; however, the General Manager, Plant Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Plant Safety Committee shall malatain written minutes of each

?SC meeting that, at a minimum, document the results of all PSC tctivities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Plant Manager, ANO-1, General Manager, Plant Operations and Chairman of the Safety Review Committee.

6.5.2 Safety Review Committee (SRC)

FUNCTION 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the

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alcas of:

a.

n'iclear power plant operations k.

nuclear engineering chemistry and radiochemistry c.

Amendment No. J$,3#,3/,47,55,$2, 122 SE PP,JWP,124 J47,147

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i ENCLOSURE 3 PROPOSED ANO-2 OPERATING LICENSE CllANGE i

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(5) EDI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive possess and use in amounts as-required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sampic analysis or instrument calibrat ion or associated with radioactive apparatus or compoients; and (6) EDI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and specini nuclear materials as may be produced by the operation of the facility.

C.

This amended license shall be deemed to contain ad is subject to conditions specified in the following Commissior. <meulations in 10 CFR Chapter I; Part 20, Section 30.34 of part 30, Section 40.41 of part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereaf ter in ef fect; ant is subject to the additional conditions specified or incorporated below:

(1) ligXlaum Power Level E01 is authorized to operate the facility at steady state reactor core power levels not in excess of 28 i megawatts

thermal, Prior to attaining this power level EDI shall comply with the conditions in Paragraph 2.C.(3).

(2) Technical Soccifications Amendment The Technical Specifications.ontained in Appendix A,

  1. 122 as revised through Amendment No. 122 are hereby incorporated 08/06/91 in the license. E01 shall operate the faci.11ty in accordance with the Technical Specifications.

Exemptiva 2nd paragraph of 2.C.2 deleted per Amendment 20, 3/3/81.

(3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the IJcense supported by a favorable evaluation by the Commission.

2.C.(3)(a) Deleted per Amendment 24, 6/19/81.

(b) Fire Prots.ction EDI shall implement and maintain in effect all provisions of the approved fire protection program as 3

1 described in Amendment 9A to the Safety Analysis Report and as approved in the Safety Evaluation Report dated subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the aoility to achieve and maintain safe sht.tdown in the event of a fire.

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s (c) Less Than Four Reac(pr Coolant Pump Oneration EDI shall not operate the reactor in operational Modes 1 and 2 with fewer than four reactor coolant pumps in operation, except as allowed by Special Test Exception 3.10.3 of the facility Technical Specifications.

2.C.(3)(d) Deleted per Amendment 24, 6/19/81.

(c) Eire Protection AP&L shall complete the following modificati os by the indicated dates in accordance with the stafi findings as set forth in the fire protection evaluatt

report, u

NUREG-0223 Fire Protection Safety Evaluation Report."

Implementation Dates fpr PronosetModifications Applicable Section of EUREG-0223 Date 3.1 Portable Radio Communication Equipment March 31, 1979 3.2 Separat]on of Power Cables in Manholes 3.3 Protection from Water Spray 3.4 Protection of Redundant Cables in the MCC Room (2096-M)

December 30, 1978 3.5 Protection of Redundant Cables in the llallway - Elevation 372 (2109-U) 3.6 Protection of Redundant Cables in the Cable Snreading Room (2098-L) 3.7 Protection of Redundant Cables in d Switchgear Room (2103-Z) 3.8 Protection of Redundant Cables in the Electrical Equipment Room (2091-BB)

September 30, 1978 4

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-. PROPOSED ANO-2 TECilNICAL-SPECIFICATION-CHANGES L

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INSTRUMENJAHON-FIRE DETECTION INSTRUMERTATION

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< FIRE DETECTION INSTRUMENTS

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-ARKANSAS - UNIT 2 3/4 3-44 Amendment No. 23, $$

PLANT SYSTEMS 3/4.7.10 PIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSIEd IdhlEHLCDNDlH01.JOR_01%R6HOS DELETED ARKANSAS - UNIT 2 3/4 7-29

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3. /4 /-37 Amendment No. yJ,jjj
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-c.

At least two 11consed Operators shall be present in the. control room'

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Jduring reactor start-up, scheduled-reactor. shutdown and.during' j

recovery from reactor trips.

d. :- - An individual qualifind-in radiation protection proceduros shall be s

.an site when funi is in the reactor, I

e..

All CORE: ALTERATIONS shall-be directly supervised by olther a j

licensed ~ Senior Reactor Operator or Senior.Roactor Operator Limited

'to Fuel llandling who has no other c,ncurrant responsibilities during this operation, j

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DELETED 1

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' Administrative. control shall be established to limit-tho' amount of.

overtimo ' worked by plant staf f ' performing safety-t elated functions.,

- Those administrativo controls shall be in accordance with the -

gu'idance provided by the NRC policy Statement on working hours 1

-(Generic Letter No. 82-12).

h.: - The Manager, Operations and Shif t Supervisor shall hold a senior reactor operator license.

ARKANSAS - UNIT 2 6-2 Amendment No. 11,2),29,51, 11,95,51, 9f,lif

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,w, gilg} STRATIVE_CO_NTR_OLS 623 'INIT STAFF OUALIFICATIONS 6.3.1 Each member of the unit staf f shall meet or excocd the minimum qualifiestions of ANSI N18.1-1971 for comparable positions, except for (1) the j

designated radiation protection manager, who shall meet or exceed the i

qua}ifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall hcve a bachelors 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.

6,4 TRAIN 1HQ l

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Training and Emergency Planning and shall meet or exceed the requirements and recommendations of Section 5.5 of A!,'SI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 DELETED 6.5 REVIEW AND AUDIT 6.5.1 PLANT EAFETY COMMITTEE (PSCJ FUNCTION 6.5.1.1 The Plant Safety Committee shall function to advise the General Manager, Plant Operations and Plant Manager, ANO-2 on el! matters related to nuclear sa fety.

COMPfaITION 6.5.1.2 The Plant Safety Committee shall be composed of eight members of ANO onsite management-organization (except as discussed under 6.5.1.3) at the superintendent 1cvel or above. The PSC Chairman shall ensure that adequate expertise is present during meetings to evaluate matorial before the PSC.

In addition, the General Manager, Plant Operations shall designate in writing a PbC Chairman and at 1ctst one Alternate Chairman.

6.5.1.3 If Core Protection Calculator (CPC) Software is being reviewed a nuclear software expe-t shall be present as a voting member.

If one of the members of the Plant fety Committee meets the qualification requirements for this position, the re.pirement to have this member is satisfied. This membership may be filled by two appropriately qualified individuals who shall ballot with a single combined vote.

Generic qualifications for this membership ahall be as follows:

ARKANSAS - UNIT 2 6-5 Amendment No. 5, J ), J 1, L

19,29,72,13.55, 95,115,1J9

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ADEATEIRATIVE CONTROLS f.

LReview of all REPORTABLE EVENTS.

g.-

Review of_ facility operations to detect' potential nucinar safety

-hazards.

h.

EPerformance of special-reviews, investigations or analyses, and' reports thereon as. requested by the Plant Manager, ANO-2,_ General Manager, Plant Operations o.

the Safety Review Committee.

1.

Review of the Plant Security Plan and implementing procedures and-submittal of recommended changes to the_ General Manager, Pla_t Operations and the Safety Review Committee.

j.

Review of the Emergency Plan and impicmenting procedures and

- submittal of recommended changes to the General Manager, Plant Operations and Safety Review Committee.

k.

Review of changes to the Offsite Dose Calculation Manual and Process Control Program.

1.

Review of changes to the fire Protection Program and impicmenting, procedures and submittal of recommended changes-to the General Manager, Plant Operations and Safety Review Committee.

AUTHORITY 6.5.1.8 The Plant Safety Committee shall:

a.

Recommend in writ tng their approval-or disapproval of items considered under 6.5.1.6(a) through (d) above,

b..

Render determinationa -in writing with regard to whether or not each itom considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety question.

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c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Operations ANO and the Safety Review Committee of disagreement between the PSC and the Plant Manager, ANO-2 or the General Manager, l

Plant Operations; hcwever, the General Manager, Plant Operations shall have responsibility for~ resolution of such disagreements

. pursuant to 6.1.1 above-.

i, RECORDS l.

6. 5.1. 9 The Plant Safety Committee shall maintain written minutes of each PSC meeting that, at. a minimum,- document the results of all PSC activities performed under the responsibility and authority provisions of these technical I

l specifications. Coples shall be provided to the Plant Manager, ANO-2, General i

Manager, Plant Operations and Chairman of the Safety Review Committee.

ARKANSAS - UNIT 2 6-7 Amendment No. 5,J/,25,52,69,

/?,tf,91, 95,JJF,JJ9 l

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