U-601138, Proposed Tech Specs Changing Onsite Organization Chart & Related Specs,Per Proposed Organizational Restructuring
| ML20196E665 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/23/1988 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20196E657 | List: |
| References | |
| U-601138, NUDOCS 8803010228 | |
| Download: ML20196E665 (8) | |
Text
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attcchnent 2 to U-601138 Page 1 of 3 Description and Justification of C6..g This proposed change offects Figure 6.2.2-1. "Unit Onsite Organization."
Specification 6.3.1. "t: nit Staf f Qualifications." and Specification 6.5.1.2 "Facility Review Group (FRG) Composition." The following changes are proposed to the onsite organizational structures The position of Technical Advisor to the Plant Manager is no longer justified and should be deleted.
The position of Director-Plant Radiation Protection vill be retitled Assistant Manager-Plant Radiation Protection.
The position of Director-Plant Technical vill be retitled Assistant Manager-Plant Technical.
The positions of Supervisor-Chemistry and Supervisor-Radvaste vill report to the Assistant Manager-Plant Technical.
The positions of Supervisor-Computer and Supervisor-Systems vill be transferred to Nuclear Station Engineering department and are no longer a
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part of the Unit Onsite Organization.
The position of Assistant Supervisor-Plant Support Services vill be established and the pocition of Administrative Supervisor will be deleted.
The position of Supervisor-Industrial Safety will report to the Supervisor-Plant Support Services.
The position of Director-Plant Radiation Protection should be changed to Assistant Manager-Plant Radiation Protection in Specification 6.3.1.
The positions of Director-Plant Technical and Director-Plant Radiation Protection should be changed to Assistant Manager-Plant Technical and Assistant Manager-Plant Radiation Protection in Specification '. 5.1.2.*
Iaais for l'o Sirnificant Hazards Corsideration According to 10CTR50.92, a proposed change to the licensc kvolves no l
significent hazards considc.ratien if eperction of tl.c ftcility in eccordance
- 1) involve a sfrnificant increase in the sith the proposed change vould notprobability or consequet.ces of en r, cidcat pre liL the possibility of a new or differo t kind of accident from eny accident previously evaluated, or (3) involv a significant reduction in e cargin of a
safety.
1)
The proposed change does not ii s olvt a significant incrose in tirThis is probability or consequences of.n accident previcusly evaluated.
es not affect current accident our. lyres.
an administrative change that 6
2)
T1.e preposed changc dect not c ' r 't c the possibility of e new er different L a.
Lind of accident fron any acc a at previously evaluated. This in an adninistrative chan n only eC f.<r,t.et affect plant der 4 gn or ope ration.
3)
The proposed change do.cs not O, Ivc
- r. rignifict.nt reduc'ien 1-a targin of safety. This is an adminirtritive change only and doe s not af fect a cargin of safety.
Attcchnent 2 to U-601138
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E-4 CLINTON - Ui1T 1
.utououent a to U-601138 Page 3 of 3 ADMINISTRATIVE CONTROLS
- 6. 3 UNIT STAFF QUALIFICATIONS bWstwrMnmeg 6.3.1 Each member of the unit staff shall eet or exceed the minimum qualifi-cations of ANSI /ANS 3.1-1978** except for the C&r+s4or-Plant Radiation Protec-I tion and the Radiation Protection Supervisor who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975.
The licensed Operators and Senior Operatcrs shall also meet or exceed the minimum qualifications of the March 28, 1980 NRC letter to all licensees.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall i
l be maintained under the direction of the Director-Nuclear Training, shall meet or exceed the requirements and reconmendations of Section 5.5 of ANSI /ANS 3.1-1978 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements i
specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
l 6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW PROUP (FRG)
FUNCTION 6.5.1.1 The FRG shall function to advise the Manager-Clinton Power Station on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The FRG shall be compose:'>
the:
Assistant Manager-Clinton Power Station Chairean:
Member:
Assistant Managcr-Plant Maintenance Member:
Assistant Manager-Plant Operation Member:
Dircetc+ Plant Technical Memte n
[
Supervisor-C&I haintenance I
Ferber:
/ /, Director Plant Pediation Protection F e::be r:
I Supervisor-huclear Pe-ber:
[
Supe rvi s e r-Cheri s try
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\\
Assista,g gapngen-
"The steff re nrted its conditional acceptance of the applicant's requeit for exce;.ticn tc ANSI /AN5 3.1-1973 quclification require-< its f ar the Clir ton Supervisor of Control and Instrumentation in NURECs Supplement N. 5.
CLINTON - UNIT 1 6-7
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- Attachment =3
.a to U-601138' E
-Pags 1 of 5.
A::ach ent 3 to U-60!'0;S-t Page 112 of 15T PACKAGE HUM 3ER 15
.0ercriccion of Change The proposed.:hange af f ects 7:gure.6.2.2-1 "Unit Casite Organization."
'The asterisks.are used.:o indicate qualification requirenents for various uni s:aff-personnel. Qualifications are addressed in Specifica:1en 6.3, "Unit Staff Qualifications," and in' Chapter 13 of the
?SAR;.therefore the asterisks shculd be deleted fres Figure 6.2.'2-L.
Main:enance and
'Additierally, the posi:icns of Diree:or - Plan:
Manager - Startup have been deleted due to cenpany Assistan:
organizational restructuring.
3 asis For No Significant Hazards Consideration According to 10CFR50.92, a proposed change to the licerse (Technical Specifications) involves no significant hazards consideration if opera: ion of'the facility in accordance with the proposed change veuld
.not (1) involve'a significan: increase in the probability or consequences of an accident previously evaluated; or (2) create the from any accident possibility of a new or different kind of accident previously evaluated; or (3)* involve a significant reduction in a =argin of safety.
(1)' The proposed change does not involve a significan: increase in the probability or consequences of an accident previously evaluated.
This change is an adninistrative change that eli=ina:es'the identification of uni staff qualification require ents on the IP's The proposed change does not affect organizational chart.co=mit:ents regardin3 the qualifications and training of u personnel.
The proposed change does not create the possibility of a new or (2)
These different kind of accident from any previously evaluated.
changes are only administra:ive changes regarding unit s:a'f.
Plant design is not affected; qualifica: ion requirenen:s, scenario has been created.
therefore no new acciden involve a significant redue: ion in a (3) The proposed change does notThese are adminis::a:1ve changes that do not
=argin of safety.
a argin of safety.
plant design and therefore do not affect i
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Attachment.3 t
-to U-601138 c-Page 3 of 5' A::ach ent'3' co U-601048 Page 114 of 137, PACKAGE NOM 3ER 16-This Tech:tiern 5;ecification change package con:ains thces separa:e changes to page 6-7 and two changes :o page 6-3.
Description of Change (1)
This change is to Specificatien 6.3 "Unit Staff Qualitications".
The exe:ption to ANSI /ANS 3.1-1978 Sec: ion 4,4.2 "Ins:ru=enta:1on and Con:rol" qualification require:ents for :he Clin:en Supervisor Control and Instru=enta: ion shculd be deleted. Mr. J Pal =er nov fills :he position of Supervisor - Control and Instrumentation and fully meets the ANSI /ANS 3.1-1978 cualification requirements.
Basis Tor No Significant Ha:ards Consideration For Change (1)
According to 10CFR50.92, a proposed change to the license (Technical Specifications) involves no significant hazards considerations if operation of the facility in accordance vich the proposed change veuld not (1) involve a significant increase in the prceability or consequences of an accident previously evaluated; or (2) create the any accident.
possibility of a new or different kind of accident-fro:
previously evaluated; or (3) involve a significant reduction in a =argin of safe:7 involve a significant increase in the The proposed change does not 1) probability or consequences of an accident previously. evaluated.
This is an ad=inistrative change that eit=inates an exe ption to a No accident analyses are affec:ed.
qualification require =ent.
create the possibility of a rev or 2)
Th' proposed change dees not any accident previously evalua:ed.
different kind of ac61 dent fro:
accident This is an ad=inistrative change and does not affec:
analyses.
involve a significant reduction in a 3)
The proposed change does notThis is an administra:ive change that re= oves an cargin of safe:y.
So cargin of safety is exe:ption to a qualification require:ent.
reduced.
Description of Chanee (2) 1ons" and 6.4 This change is to specification 6.3 "Unit Staff Qualifica: sentence should be delet In Sp.scification 6.3, the las:
"Training."
as it has been superseded by the 1937 version of 10CTR55, "Operators Additionally, the phrase "and the Radiation Protection During the licensing process, the ti:la Licenses".
Supervisor" should be deleted.
Radiation Protection Supervisor to of this individual was changed fro:This change was fersarded to the NRC Director - Radia:Lon Pro:ee:1on.
Specification 6.4 should but deletion of :he old ti:le was overicoked.
he modified as indicated en the attached =arked page :o delete 4:arial that has also been superseded by the 1937 versi:n of 10CTR55.
4
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Attachmsnt 3
=
to U-601138
' ; j.l.,
Page 4'of 5
. Attach =ent 3' to C-601048 Page'115 cf 157' The required.ac.ts:of the March 23, 1930 letter, were incorporated as-appropriate by the NRC into the 1987 version of 10CTK55-Descriptien-of Change (3)
'This change is to Specifica icn 6.4 and to Figure 6.2.1-1.
In January
~
1988, the position of Director - Nuclear Training vill be upgraded co Manager.- Nuclear Traiaing. The two referenced Specifications should be updated accordingly.
Additionally, the word "operations" under the Manager - feheduling.and, Cutage Manage:ent shculd be replaced with "staff" in order to be consistent with the rest of the organi:ation chart.
and (3)
Basis For No Significant Hazards Consideration For Changes (2)
According to 10CTR50.92, a proposed change to the license (Technical Specification) involves no significant hazards consideracida if operation of the facility in accordance with the proposed change veuld not (1) involve a significant increase in the prcbability or consequences of an accident previously evaluated; or (2) create the f c= any accident possibility of a new or.different kind of accident reduction in a margin previously evaluated; or (3) involve a significant of safety, increase in the The proposed change does not involve a significant f
(1) possibility or consequences of an accident previously evaluated because these changes are merely ad inistrative in nature and do net affect any accident analyses.
(2) The proposed change does not create the possibility of a new or different kind of accident f rom any previcusly evaluated because these changes are administrative and de not affect plant design.
The proposed change does not involve a significant reduction in a (3) margin of safety because these are ad=inistrative enhancenents to 4
operation and do not affect the margin of safety, i
6 O
to U-601138 Page 5 of 5 A:: a c h..e r. : 3
- o 'J-60'C;5
? age l '. ' o f ' 5 '
A:9:NISTRATIVE CCNTROLS 6.3 UNIT STAFF CUALIFICATICNS Each member of the unit staff shall meet or ex:ee 6.3.1 cations of ANSI /ANS e
ti0n a:d the 'td' t'en Prot ++t':- 5;; ;':: wnc shall meet er ex:eed the quali-L: :: ::: ::: :::-: :- -
f t:sticas of Regulatory Guide 1.3, Se;tember 1975.
~ M-ee-::e :te ;
':: ::: : ;;;;;d tre n' 'r.: ;.C ifi::*.': :- f :
- Mc :- 22, '.??: 9 *: 'ett:- t: :' ' ' 4 : : e s, 6.4 TRAINING nuer ana am for the unit sta'j!shall g
be maintained ur. der the directi0n of the Dir.pr0grA retraining a
- 6. 4.1 n
- f ~;;t' - 5.5 :' A.N */AN' er ex:eed the require:er,ts a-d :::. : ::t':n';; e ndi " A' c f 10 CF R P art 55 eren 3, ;; 4_3.-
- ,,;;e.
-3.'. '." C a-a '"ed f- !a:t': : + a n d C c ' Eae4se=: 1 at-the u t: 2' 'f ee es+:, ard :h:" inca d: f: ic-i::t'Or with
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6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW GRCUP (FRG)
FUNCitCN The FRG shall function to advise the Manager-Clinton Power Station en 6.5.1.1 all matters related to nuclear safety.
CCHFCSIT!C_N
- 6. 5.1. 2 The FRG shall be cc.rpesad of the:
Assistant Ma ager-Clinton P:wer Station Chairman:
Assistant Manager-Plant Maintenance Me:te r:
Assistant Manager-Plant C;eration Me::e-:
Director Plant Te:hnical Mester:
Su;ervisor-CAI Maintenance Me:ber:
Director Plant Radiation Prete: tion Metter:
Superviser-Nuclear Me:ter:
Supe rviscr-Chemi stry Me:be r:
4
[
- Tne staf f re;ceted its condittenal a :eptance of tne a:olicant's re: west for exception to ANSI /ANS 3.1-1978 qualification re uirements for the Clint n
^
Su:plement No. 5.,,/
N~~~iceervisor of Control and Instr. mentation in NURE3 Ci!3, 6*7 CLINTCH - UNIT 1