ML19350C195

Tech Specs 3.2,6.2 & 6.4 Mods to DNB Parameters,Facility Organization & Plant Operations Review Committee Composition

ML19350C195
Person / Time
Site:	Sequoyah
Issue date:	03/25/1981
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19350C193	List: ML19350C192 ML19350C195
References
NUDOCS 8103310506
Download: ML19350C195 (5)

Text

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v ENCLOSURE 1 PROPOSED CHANGES TO SEQUOYAH NUCLEAR PLANT UNIT 1 TECHNICAL SPECIFICATIONS i

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TABLE 3.2-1 .

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.DNB PARAMETERS

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, ,g; LIMITS

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.5I PARAMETER'- -

Operation Operation **_

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. Reactor. Coolant' System T: 4 5830F ,

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I J Pressurizer Pressure  :> 2220 psia *' .

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w c* .. Limit not applicable during a THERMAL ~ POWER ramp in excess of'5% RATED Ti!ERMAL POWER l 7 perlminu'te, a: THERMAL POWER. step in.e.xcess;of.10% RATED TllERMAL POWER, PIIYSICS TEST, i

G. or performance of : Surveillance

• Requirement 4.1.1.3.bg 4

(** Limits pendi6g NRC approval of'3 loop operation.

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PLANT SUPERHTENDENT OUALnY

- ASSURANCE

. SUPERVISOR ENGNEERN'IOPERATONS l HEALYN 4 SAFETY SERVCES MANT(NANCE ,, { ,, ,

' ASSISTANT ASSISTANT , ASSISTANT l OUTAGE l PLANT, PLANT. PL ANT I I e

DEMR l SUPERWTENDENT SUPERNTENDENT SUPERNTENDENT u__-__a

, ,.-------i r --- -- -- i i ~ l_ I l i i - MEDCAL , , SECURITY ..

L. - - ., s. _ - _ _ _ _ _ i r-------i HEALTP ,

- PHYSCS p POWER STORES l '

, ,_ SUPERvC . ; 1, _ _ _ _ _ _ ;

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^ MECHL MANT S ENGINEERNO I . PREOP TEST 1 OPERATONS 'l ELEC MANT l l ER OR

- SECTON I . SECTON ' SECTON . b - - _ = _ _ _8 SECTON SECT #M4 e PSO 8 SUPERVISOR . iSUPERVISOR 8

. -SUPERVISOR '

u___ i i i-L_-______8 ASSISTANT ENGG ASStSTANT . SAFETY PLANT *' j g i i

' SECTON . OPERATONS SECT ENGINEERNG COMPLIANCE SUPERVISOR SUPERvlSCet MECHL MANT GEN MECHL ELEC MANT GEN ELEC SUPERVISOR _ .. SUPERVISOR .pt SUPERVIS% FOREMAN UNIT SUPERVISOR FOREMAN CHEMICAL UMT" ENGNEERNO .& OPERATONS SUPERVISOR TEST UNIT SUPERVISORS MANAGEMENT JANITORIAL 8 SUPERVISOR SERVCES , LABORLR 3

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.i . REACTOR t SUPERVISOR SUPERVISOR 4

ENGHEERNG

, ' UNIT '

. - SUPERVISOR ,

I i i I N NT ADMNISTRATIVE CONTROL SERVCES UNIT

"--"""""I. SUPE VISOR SUPERV8SOR UNIT SUPERVISOR FOREMAN l- RE' PORTS FUNCTIONALLY AS e

,_ _ j NDCATElk ADMINGSTRATIVELY OFFSITE -

PLANT

• ISEG FUNCTONS ARE ARE ASSIGNED SERVCES UNIT TO PLANT COMPLIANCE STAFF SUPERVISOR FIGURE 62.2 FACILITY ORGANIZATON - SEQUOYAH UNIT 1 O

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ADMINISTRATIVE CONTROLS i

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Assistant Plant Superintendent of Operations - and Engineering and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and i Appendix "A" of 10 CFR Part 55 and the supplemental requirements spe.cified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry 1

operational experience identified by the ISEG.

6.5 REVIEW AND AUDIT 6.5.0 The Manager of. Power is responsi.ble for the safe operation of all TVA power plants. The functional organization for. Review and Audit is shown on Figure 6.2-1.

6.5.1 - PLANT OPERATIONS REVIEW COMMITTEE (PORC)

- FUNCTION 6.5.1.1 The- PORC shall function to , advise the Plant Superintendent on all matters related to nuclear. safety.

- COMPOSITION 9

- 6.5.1.2 The PORC shall be composed of the:

Chairman: Plant Superintendent or .his representative Member: Operations'Section' Supervisor ~

Member: Engineering.Section Supervisor Member: - Electrical Maintenance Section Supervisor

, Member: Mechanical Maintenance Section Supervisor

l. Member: Instrument Maintenance Section Supervisor Member: Health-Physics Supervisor Member: ' Quality Assurance Supervisor t

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SEQUOYAH.- UNIT 1 6-7a-4 4 s F / f

• ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT UNIT 1 JUSTIFICATIONS FOR PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS Figure 6.2-2 and Page 6-7a

.This change involves. a revision of the plant organization and resulting changes to PORC composition.

The. plant organization has been revised to decrease the span of control for Assistant Plant Superintendent positions and permit closer involvement by

, Assistant Plant Superintendents in day-to-day plant operation.

Table 3.2-1

'During the power coefficient measurement (PHYSICS TEST) and' in the performance of S.R. 4.1.1 3.b, it is very difficult to maintain pressurizer pressure 1222Qpsia. The reactor coolant system Tavg must be dropped a minimum.or.4-6 F below the. programmed Tavg for an accurate measurement.

' The associated drop in: pressurizer level results in a downward swing of pressurizer pressure and 2220 psia is difficult to maintain.

The -NgC already: recognizes the need to operate the plant at less than 2220 lb/in a for short periods of time. This is evident by the present footnote to Table 3.2-1 (the -pressure limitation is not applicable during a thermal

power ramp in excess 7 of 5 percent rated thermal power per minute or a'

thermal power step. increase'in excess of 10 percent rated thermal power).

'The -limit .on pressurizerp' ressure is placed on the plant to validate a

' safety- analysis assumption -for pressure.at the . time of an accident.

The time spent' at .12220 'lb/in a for physics test and during performance of Surveillance LRequirement 4.1.1 3.b is mini'mal.- Therefore, 'the likelihood of an ' accident occurring during this time is remote.

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