ML20070E222

Application for Amend to License NPF-42,revising Tech Spec Section 6.0 to Reflect Miscellaneous Changes to Administrative Controls at Facility

ML20070E222
Person / Time
Site:	Wolf Creek
Issue date:	02/27/1991
From:	Rhodes F WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070E225	List: ML20070E222 ML20070E230
References
NUDOCS 9103050227
Download: ML20070E222 (9)

Text

.  !

I

~

WMF CREEK NUCt. EAR OPERATING CORPORATION

(,% M,** february 27, 1991 enea nno a 1.cnnieat him U. S. Nuclear Regulatory Connission ATTH: Document Control Desk 1 Hall Station P1 137 Washington, D. C. 20555 i

Subject Docket No. 50-482: Revision to Technical Specification l Section 6.0 . Administrative Controls Gentlemen: I The purpose of this letter is to transmit an application for amendment to I Facility Operating License No. NPF-42 for Wolf Creek Generating Station j (WCGS), Unit No. 1. This license amendment request proposes revising  !

Technical Specification Section 6.0 to reflect rniscellaneous changes to the administrative controls at WCGS.

Attachment I provides a description of the amendment along with. a Saiety i Evalua+.lon. Attachment 11 provides the Significant Hazards Considerat 'on l Determination. Attachment III provides the Environmenta. Impact  !

Determination. The proposed change to the Technical Specificatior,is -

provided as Attachment IV. l i

In accordance with 10 CPR 50.91, a copy of this application, with attachments. is being provided to the designated Kansas State Official.

If you have any questions concerning this matter, please contact me or l' Mr. H. K. Chernoff of my staff.

Very truly yours.

l p vt /

Forrest 7. Rhodes  !

Vice President l Engineering & Technical Services i FTR/jra-1 Attachments: I --Safety Evaluation 1 II . Significant Hazards Consideration Determination III - Environmental Impact Determination IV - Proposed Technical Specification Changes cci G. W. Allen (KDHE), w/a I A. T. Howell (NRC), w/a R. D. Hartin (NRC), w/a p0 D. V. Pickett (NRC), w/a M. E. Skow (NRC), w/a i

" 8 ""'*""^** * " " 18 * **

$103nso 27 91o227 An tquel Oppetunny Envoy, M rHCNET FDR 'ADOCL 05000482 P PDR

.gmomy - -

-m . .. - -

b 0 ,1

-t c

b i

4 8 4 I k

t t

t

) .

1

[,

5 4

e

,a a

I

?

i

)

r I

-t I

-A b

+

- ll .

P t

li 4

w I..

• T 4 4 4

+

a

?

4 L

.--.-....E5..- .- --- -

mm _w

STATE OF KANSAS )

) SS COUNTY OF COFFEY )

Forrest T. Rhodes, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering and Technical Services of k'olf Creek Nuclear Operating Corporations that he has read the foregoing document and knova the content thereof that he has executed that same for and on behalf of said Corporation with full power and authority to do son and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

L By Forrest T. Rhodes Vice President Engineering & Technical Services SUBSCRIBED and sworn to before me this 47 dayof70ds ,

1991, g, h64 Notary Public ntAL g

s . * * ",', ";,. ' , ' . .

Y /fff T, Expiration Date MW W J

. Y 1; ( V '

+4,

• . , ' . . . . .de*'ye

)h .!(( l 6

, ,s o

A4 & h.-a EJB4 EM p&-4.a.AA -Ohea.m Ae. p4AMmed 4 hem he A 4 e M .6h e ma a 4 M M e4,sM' ' - ' -

• aE J, & ,6-.t.M#M .ESAhe.h Wh-44.h b " ^

^h ew@d#,M4 'h a J ,A m $_& 5 4 4_,6 e

. . t t 9

9 b t

r f

+

t i

t s

e C

i e

. i h

+ ., .'

- I

.y i+4 f

i: e

• t l f' .%..

'4 a p _

4 ,_ (-  !

s

-A~ ~' .' f,5 er t

h 4,

)

a a Y

l l

3 I

i i-

- W1M ' V4TFT veeW44+dNm'D'- E +-W O-rww W ym 9 -

I e

Attochmont f to ET 91 0040 Page 1 of 3 }

ATTACIMENT I SAFETY EVALIIATION l

-9  %

i t

i I

e 4

I k .

I l 4

1 1

1 i

J' 3

i s

i

,. 6%wted a weug 's--

h#54*f'~---br-' heat-- >+w++ -*m9-m ..vm-tm veems M _. _ . . , .'u*@vw" 4+- w1-w w T3vWT4 WW'99'-'w$'YN 44FTF W 7WWw+W"'9TYW"TT-t O TT"#'

l , .

Attachment I to ET 91 0040 Page 2 of 3 Safety Evaluation Proposed Change The purpose of the proposed Technical Specification changes is to revise Section 6.0 to reflect miscellaneous changes to the administrative controls at Wolf Creek Generating Station.

Evaluation The title of Operations Supervisor in Technical Specification Section 6.2.2.g. is being changed to Supervisor Operations. Additionally, Section 6.2.2.g. is being changed to require either the Supervisor Operations or Manager Operations to hold a senior reactor operator license. This change provides flexibility to the organization during the licensed operator requalification examination process and still provide a licensed individual for supervision of the shift crews.

Table 6.2 1, Minimum Shift Crew Composition, is being revised to be consistent with Section 6.1.2 of the Technical Specifications. The proposed revision to Table 6.2-1 would replace the incorrect references to the Shift Supervisor command and control function with references to the Supervising Operator function. In Standard Technical Specifications the control room command function is the responsibility of the Shift Supervisor. However, Section 6.1.2 was modified from the Standard Technical Specification to indicate that the Supervising Operator shall be responsible for the control room command function during initial licensing of Wolf Creek Generating Station (WCGS). Table 6.2-1 is further being modified to clarify that an appropriate licensed individual, can assume both the control room command function and the Shift Technical Advisor (SAT) function. The use of the dual-role Senior Reactor Operator (SRO)/STA was approved for WCCS in NUREG-0881, ' Safety Evaluation Report related to the operation of Wolf Creek Generating Station, Unit No. l', Supplement 5. On February 13, 1986 Generic Letter 86-04, ' Policy Statement on Engineering Expertise on 6hitt' vac issued in which the NRC encouraged licansees to move toward the dual.

role SRO/STA position. Therefore, it is acceptable that during the absence of the Supervising Operator from the control room an appropriate licensed individual, dependent on Unit HODE, can assume both the control room command function and the STA function.

Technical Specifications Sectiono 6.3 and 6.4 are being revised to be consistent with the basis for 10 CFR Part 55 to require Licensed Operators and Senior Operators to meet or exceed the training and qualifications of ANSI /ANS 3.1 1981 as endorsed by Regulatory Guide 1.0, Revision 2,

' Qualification and Training of Personnel for Nuclear Power plants'. On March 25, 1987, 10 CFR Part 55 was amended to clarify the extent to which simulators should be used in licensing examinations and to reflect upgrr'ed requirements for licensed operator selection, training and requalific' ion programs resulting from the accident at TMI-2. Subsequently, the NRC is aed Revision 2 to Regulatory Guide 1.8 which provides a method acceptable l

Attachment I to ET 91-0040 Page 3 of 3 to the NRC staff for complying with 10 CFR Part $$ with regard to the training and qualifications of nuclear power plant personnel. The requirements in 10 CFR Part $$ and associated documents are more restrictive than Sections A and C of the enclosure to the March 28, 1980 NRC letter to all licensees. This revision is an administrative change which revises sections of the Technical Specifications by deleting outdated references and does not impact plant components, systems or equipment.

Based on the above discussions and the considerations presented in Attachment II, the proposed changes do not increase the probability of occurrence .or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis reports or create a possibility for an accident or malfunction of a different type than any previously evaluated in the safety analysis reports or reduce the margin of ' safety as defined in the basis for any technical specification.

Therefore, the proposed changes do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard.

/.ttachment II to ET 91-0040 Page 1 of 2 ATTACIMENT II SIGNIFICANT !!AZARDS CONSIDERATION DETERMINATION 1-

4 Attachment 11 to ET 91-0040 Tage 2 of 2 Significant llamards consideration Determination The proposed changes would revise Technical Specification Section 6.0 to reflect miscellaneous changes to the administrhtive controls at Volf Creek Generating Station (WCGS).

Standard 1 - Involves a Significant increase in the Probability or Consequences of an Accident previously Evaluated The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. These changes involve an administrative change and as such, have no effect on plant equipment.

Standard 2 - Create the Possibility of a New or Different Kind of Accident from any Previously Evaluated The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. These changes either do not impact or upgrade the training and qualifications of personnel who operate VCGS. These ch ngen do not involve any change to the installed plant systems or the overall operating philosophy of VCGS.

Standard 3 - Involve a Significant Reduction in the Hargin of Safety The proposed changes are an administrative change and do not involve a significant reduction in a margin of safety.

Based on the above discussions it has been determined that the requested Technical Specification revision does not involve a significant increase in the probability or consequences of an accident or other adverse condition over previous evaluations: cr create the possibility of a new or different kind of accident or condition over previous evaluations or involve &

significant reduction in a margin of safety. The requested license amendment does not involve a significant har,ards consideration.

l_ - __ __ _ _. _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___________ . _ . _

Attachment III to ET 91-0040 Page 1 of 2 ATTACIMINT III INVIR0feUMTAL IMPACT DET12HINATION

Attachment III to ET 91-0040 page 2 of 2 Envirotunental Impact Determination 10 CFR 51.22(b) specifies ths criteria for categorical exclusions from the requirement for a specific environmental assessment per 10 CFR 51.21. This amendment request meets the criteria specified in 10 CPR 51.22(c)(9).

Specific criteria contained in this section are discussed below.

(1) the amendment involves no significant hazards consideration l As demonstrated in the Significant liarards Consideration Determination in 1 Attachment II, the requested license amendment does not involve any significant hatards considerations.

(ii) there la no significant change in the types or eignificant increase in the amounts of any effluents that may be released offsite The requerted license amendment involves no change to the facility or operating procedures which would cause an increase in the amounts of effluents or create new types of effluents.

(iii) there is no significant increase in individual or cumulative occupational raniation crposure The nature of the changes is administrative and does not require additional exposure by personnel nor effect levels of radiation present. The proposed change does not result in significant individual or cumulative occupational radiation exposure.

Based on the above it is concluded that there will be no impact on the environment resulting from this change and the change meets the criteria

• upecified in 10 CFR 51.22 for a categorical exclusion from the requirements of 10 CFR 51.21 relative to specific environmental assessment by the Commission.

.