ML20005B846

Amends 64,55,74 & 67 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,modifying Tech Specs to Require Presence of Shift Technical Advisor W/Specialized Training in Reactor Technology

ML20005B846
Person / Time
Site:	Dresden, Quad Cities
Issue date:	08/21/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20005B847	List: ML20005B846 ML20005B848 ML20005B849
References
NUDOCS 8109020364
Download: ML20005B846 (20)

Text

=.

~. -......

1

'o, UNITED STATES 8

1 %

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

• \\,,,,.*/

COMMONWEALTH EDISON COMPANY j

DOCKET NO. 50-237 1

l DRFSDEN STATION UNIT NO. 2 j

AMENDMENT TO PROVISIONAL OPERATING LICENSE 1

Amendment No. 64 License No. DPR-19 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated September 18, 1980, complies with the standards ar.d requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of,the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activitie:; will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common dafense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Provisional Operating License No. OPR-19 is hereby amended to read as follows:

3.8 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.64, are hereby incorporated in the 1icense.

The licensee shall operate the facility in accordance with the Technical Specifications.

8109020364 810921 '

FR ADOCK 05000237J p

l PDR i

_. 1 i

e 4

a I 3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/1 Dennis M. Crutchfield, Chi Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 21, 1981 8

7-O 3

ATTACHMENT TO LICENSE,44ENDMENT NO. 64 PROVISIONAL OPERATING LICENSE NO. DPR-19 1

DOCKET NO. 50-237 Revise the Appendix "A" Technical Specifications as follows:

Remove Replace 158 158 161 161 l

t

't l

5 I

.i

.=

DPR-19 6.0 ADMINISTRATIVE CONTROLS i

6.1 Organization, Review, Investigation and Audit A.

The Station Superintendent shall have overall E.

Retraining and replacement training of Station full-time rest.cnsibility'for safe operation of personnel shall be in accordance with ANSI N18.1, the facility. During pe'riods when the Station

" Selection and Training of Nuclear Power Plant Superintendent in unavailable, he shall desig-Personnel," dated March 6, 1971.

(

nate this responsibility to an established alternate who satisfies the ANSI N18.1 exper-A training prograss for the fire brigade shall be i

ience requiremente for plant manager.

maintained under the direction of the Operating Engineer and shall meet or exceed the requirements -

t B.

The corporate management which relates to the of Section 27 of the NFPA Code - 1975, except for operation of this station is shown in Figure fire brigade training sessions which shall be held 6.1.1.

at least quarterly.

i l

C.

The normal functional organization for opera-F.

Retraining shall be conducted at intervals not ex-l tion of the station shall be as shown in ceeding two years.

t j

Figure 6.1.2.

The shifr manning for the station I

shall be as nhown in Table 6.1.1.

G.

The Review and Investigative Function and the Audit Function of activities affecting quality during j

?

D.

Qualifications of the station management and facility operations shall be constituted and have the I

operating staff shall meet minimum acceptable responsibilities and authorities outlined below:

}

{f levels as described in AHS! N18.1, " Selection and Training of Nuclear Power Plant Personnel,"

1.

The Supervisor of the Offsite Review and Investi-t I

dated March 8, 1971 with the exception of the gative Function shall be appointed by the Vice Hadiological Chemical Supervisor President of Construction, Production, Licensing, i

who shall meet or exceed the qualifi-and Environmental Affairs. The Audit Function i

cations of Regulatory cuide 1.8, September, 1975 shall be the responsibility of the Hanager of and

• the Shift Technical Advisor wto shall Quality Assurance and shall be independent of have a bachelor's degree or equivalent in a operations.

4 scientific or engineering-discipline with speci-fic training in plant design, and response and a.

Offsite Heview and Investigative Function unalysis of the plant for transients and acci-dents The individual filling the position of The Supervisor of the Offsite Heview and In-Adininistrative Assistant shall nieet the minimum vestigative Function shall:

(i) provide

. I acceptable level for " Technical Manager" as de-directions for the review and investigative j l scribed in 4.2.4 of ANSI N18.1 - 1971.

function and appoint a senior ref:icipant to j i provide appropriate direction, (ii) select i

A fire brigade of at least 5 members shall be each participant for this function, (iii)

{

maintained on-site at all tinies. ~1his excludes select a complement of more than one parti-the shift crew neceasary for safe shutdown of cipant who collectively possess background 1

the plant and any personnel required for essen-and qualifications in the subject matter j

tial functions during a fire emergency.

under review.to provide Amendment No. 64 158

O I

DPR-19 TABLE 6.1.1 MINIMUM SHIFT MANNING CHARTf f

n CONDITION I

CONDITION OF i

NO. OF MIh IN EACH FOSITION l

LS0*j NO.8-RAD j LIC. l. MEN OF ONE SECOND UNIT THIRD UNIT STA ' LO*

UNIT

(

I i

I Cold Shutdown 1*

O 3

5 1

l Cold Shutdown l

t i

l I

! Cold Shutdown Refuel 1**

f O

j 3

l 5

l 1

l i

+

COLD Cold Shutdown Above Cold 1

1 3

5 1

I g

t Shutdown SHUTDOWN

)

2**

l i

0 l

3 i

'S 1

l Refuel i

R2 fuel i

i I

t i

6 l

i 5

1 i

Refuel Above Cold i

2 i

1 3

Shutdown I

i i

l l

Above Cold l

Above Cold 2

{

l 3

l 5

1 g

l

[

t I

Shutdown Shutdown s

t Refuel Refuel 2

0 i

4 5

1 i

i l

t I

i i

REFUEL Refuel Abote Cold 2

1 I

4 5

1 l

?

Shutdown f

j l

i Above Cold Above Cold 2

1 j

4 5

1 l

Shutdown Shutdown I

l l

i Above Cold Above Cold 3

1 l

4 5

i 1

ABOVE COLD Shutdown Shutdown I

I SHUTDOWN STA

- Shift Technical Advisor LSO

- 1.icensed Senior Operator LO

- Licensed Operator NON-LIC. - Equipment Operators and Equipment Attendants RAD MEN - Radiation. Protection Men

- Shall not operate units on which they are not licensed.

- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervisir CORE OPERATIONS.

- Shift crew composition may be less than the minimum requirements for a period of time 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 accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew co= position to within the minimum re-g quirements of Table 6.2.2-1.

Amendment No. 64

f[

]

o UNITED STATES g

e o

NUCLEAR REGULATORY COMMISSION

$,g '

... E wAsmNGTON. D. C. 20655 Y** m /

}

COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN STATION UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE s

Amendment No. 55 License No. DPR-25 1.

The Nuclear Regulator.y Comission (the Comission) has found that:

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated September 18, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the ru:es and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Facility License No. DPR-25 is hereby amended to read as follows:

3.8 The Technical Specifications contained in Appendix A, as revised through Amendment No. 55, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Tecnnical Specifications.

)

; I!

a 3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMISSION 00^.

Thomas Ippolito, Chief Operating Reactors Branch #2 F

Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 21, 1981 i

e

l N.

l ATTACHMENT TO LICENSE AMENDMENT NO.55 4

FACILITY OPERATING LICENSE NO. DPR-25 DOCKET N0. 50-249 I

Revise the Appendix "A" Technical SpecificatiJns as follows:

Reve Replace 158 158 161 161 i

h

DPH-25 6.0 ADMINISTRATIVE cot 4THOhS 6.1 Organization, Review, In: vest igat ion and Audit A.

The Station Superintendent shall have overall E.

Retraining and replacement training of Station f

full-time ausponsibility for safe operation of personnel shall be in accordance with ANSI N18.1, the facility. During periods when the Station "r, election and Training of Nuclear Power Plant Superintendent in unavailable, he shall desig-Personnel," dated Harch 8, 1971.

nate this responsibility to an established alternate who satisfice the ANSI N!8.1 exper-A training program for the fire brigade shall be ience requirements for plant manager, inaintained under the direction of the Operating

(

Engineer and shall meet or exceed the requirements B.

The corporate management which relates to the of Section 27 of the NFPA Code - 1975, except for l

operation of this station is shown in Figure fire brigade training sessions which shall be held 6.d.1, at least quarterly.

C.

~lhe nosmal functional organization for opera-F.

Retraining shall be conducted at intervals not ex-t ion of the station shall be as shown in ceeding two years.

I i

Figure 6.1.2.

The shitt manning for the station shall I.e as shown in Table 6.1.1.

C.

The Review and Investigative Function and the Audit I

Function of activities affecting quality during D.

Qualifications of the station management and facility operations shall be constituted and have the operating staff shall meet minimum acceptable responsibilizies and authorities outlined below:

levels as described in ANSI N18.1, " Selection and. Training of Nuclear Power Plant Personnel,"

1.

The Supervisor of the Offsite Rev!cw and Investi-dated March 8, 1971 with the exception of the gative Function shall be appointed by the Vice Radiological Chemical Supervisor President of Construction, Production, Licensing, I

who shall $.A t or exc.;ud the qualifi-and Environmental Affairs. 'the Audit Function cations of itegulatory Guide 1.8, Septembar, 1975 shall be the responsibility of the Hanager of and

• the Shift Technical Advisor who shal]

Quality Assurance and shall be independent of have a b'achelor's degree or equivalent in a operations.

scientific or ungineering discipline with speci-fic training in plant design, and response and a.

Offsite Review and investigative Function analysis of the plant fer transients and acci-dents The individual filling the position of The Supervisor of the Of fsite 1:eview and In-Administrative Ass'istant shall meet the minimum vestigative Function shall:

(i) provide acceptable level for " Technical Manager" as de-directions for the review and investigative scribed in 4.2.4 of ANSl~ N18.1 - 1971, function and appoint a senior participant to provide appropriate direction, (ii) select A fire brigade of at least 5 members shall be cach participant for this function, (iii) maintained on-site at all t imes. This excludes select a complement of more than one parti-the shift crew necessary for safe shutdown of cipant who collectively possess background the plant and any personnel required for essen-and qualifications in the subject matter i

tial functions during a fire emergency, under review to provide I

i Amendment No. SS 158

[

j e

DPR-25 i

TABLE 6.1.1 l

MINIMUM SHIF7 MANNINC CHARTf CONDITION I

CONDITION OF i

NO. OF ME!; IN EACH ?OSITICN l

LSO. j i NON-l RAD 0F ONE STA ' LO* I LIC. I MEN UNIT SECOND UNIT THIRD UNIT l

?

I j

Cold Shutdown Cold Shutdown 1*

0 3

5 1

i I

t 1** l.

O 1

i l Cold Shutdown Refuil i

3 5

1 I

l COLD l

1

[

' Cold Shutdown Above Cold 1

1 3

I 5

, Shutdown l

I l

l i

SHL'I'DOWN l

2** ;l O

3 5

1 l

Refuel l

Refuel g

i Refuel Above Cold 2

i 1

l 3

S 1

I l

[

j Shutdown j

Above Cold l

Above Cold j

j 2

1 3

j 5

1 g

i Shutdown Shutdown i

1 l

1 i

I Refuel Refuel 2

0 4

5 i

i I

[

r Re fuel' Above Cold 2

1 l

4 5

1 l

REFUEL Shutdown f

l I

t 4

5 1

Above Cold Above Cold 2

1 l

l Shutdown Shutdown 4

i l

l ABOVE COLD Above Cold Above Cold 3

1 l

4 5

i 1

SHUTDOWN Shutdown Shutdown I

i STA

- Shift Technical Advisor LSO

- Licensed Senior Operator LO

- Licensed Operator l

NON-LIC. - Equipment Operators and Equipment Attendants l

RAD MEN - Radiation. Protection Men l

l

- Shall not operste units on which they are nec licensed.

- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE OPERATIONS.

l f

- Shift crew composition may be 1ers than the minimum requirements for a period of time 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 accommodate unexpected absence of on duty shift crew membere provadt.d immediate action is taken to restore the shift crew composition to within the minimum re-f,,,

quirements of Table 6.2.2-1.

Amendment No. 55 il

e UNITED STATES E

NUCLEAR REGULATORY COMMISSION j

{

E WASHINGTON, D. C. 20565 1

• %,,,,..F COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY f

DOCKET NO. 50-254 QUAD CITIES UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-29 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Commonwealth Edison !cmpany (the licensee) dated September 18, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Conmission's regulations; D.

The issuance of this amendment will not be inimical to the commoq defense and security or to the health and safety of the public, and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B cf Facility License No. DPR-29 is hereby amended to read as follows:

3.B Technical Specifications The Technical Specifications containea in Appendices A and B, as revised through Amendment No. 74, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

1

?

e

\\

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY CO M ISSION 1

Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 21, 1981 i

n

,1

I e

e t

j

.TACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 1

Revise the Appendix "A" Technical Specifications as follows:

Remove Replace 6.1-1 6.1-1 Figure 6.1-3 Figure 6.1-3 s

l' L!

CUAD CITIES DPR-29 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, INVESTICATION, AND AUDIT A. The Station Supermtendent shall hase overall ' '.l. time responsibdity for safe opera' ion of the facdity. During periods when the Station Supermtendent is unavadable, he shall deuenste this responsibihty to an estabbshed alternate who satisfies the ANSI NIS.] of \\ larch 8.1971 expertece requirements for piant manager.

B.

T5 e corporate management which relates to the operation of this station is shown in Figurt 6.1 1.

t C. The normal functional oraanization for operation of the station shalt be as shown m Figu;e 6.10. The snitt manne; for the station shall be shown in Figure o.l.3. The individual tdhrig the position et Aiministrative Assi> tant slull meet the minimum acceptable 'evel for "Techziieal Slanager" as described a Section 4.2.4 of ANSI N18.1 1971.

A fire brigade of at least 5 members sha!! be maintained on. site at all times. This excludes the shift crew necessary for safe shutdown of the plant, and any personnel required forother enential funstions Jurmg a tire emergency.

D. Qualifications of the station manacement and operating staff shall meet mimmum acceptable levels asdescribed m ANSI N18.1, " Selection and Trammg of Nue! car Power P!ar' ?ersonrier', dated Starch 8.1971. The Rad / Chem Supervisor shall meet the requirements of radiation protcetion manager of Reirulatory Guide 1.3. The Shift Technical Advisor-shall have a bachelor's decrea or equivalent in a scientific or enginecring discipline with snecific training in plant design, and response and analysis of the plant for transients and accidents.

E.

Retraming a.id replacement trainmg of Station personnel sha!! be in accordance with ANSI N18.1,"St!cction and Training of Nuclear Power Plant Personnel", dated Starch 8,19 71.

A training program for the fire brigade shall be maintamed under the dt Trion of the Station Fire Marshal. and shall meet or exceed the requirements of Sectioni 27 of the NFPA Code-li75 except that traming sessions shall be at least quarterly.

F. Retraining shall be catucted at intervals not exceeding 2 years.

G. The Review and Investiptiu Function and the Audit Function of activities affecting quality during faedity opera.

tions shall be constituted and have the respenbdities and authorities outlined below:

1.

The Supervisor of the Offsite Review and Investnrative Function sull be appomted by the Vice Preudent of Construction, fAoduction. I.ieensing and Environmental Atfa.rs. The Audit Function shall be the responsibility of the \\ tanager of Quahty Assurance and slull be independent of operations.

a.

Offsite Review and Inveutgative Function tie Supemsor of the Offute Revaw and Investigative Furetion shall: (1) provide directions for the review and t.vestiiptive function and appoint a iemor particpant to provide approprute direction.C) select each partie:prit for this funetton. (3) select a comdement of more than one participant who i

l collectively possess background and cuahfications in the si.bject matter under review to proside com.

(

prehendve interdisciplinary review coverage under this functica,(4) mdependently review and approve the finctngs and recommendations developed by personnel performing the review and mvestigative I

function. (5) approve and report m a timely manner all fmdings of noncompliance w'th NRC require-ments to the Station Supe mtendent. Division.ilanager Nuclear Stations, Slanagar of Quahty Assurance, and ti.e Vice President of Construction, Production 1.icensmg at:d Environme: tal Atfatts.

During periods when the Suoervisor of Offsite Rev:ew and Investigative Funetton is unavdable, he l

shall designate this responubdity to an established alternate. who satisfies the formal trauung and ex.

l peruce requiremer ts for the Supervisor of tue Otfsite P.eview and Investagstive Function. The responsibdities of the personnel performing this furttwn a e stad below. The Of fsite Review and

• Investrgatise F'inct.on sui! reuew:

1) The safety evatiutions the II) thanres to procedures. eu pment. or systems as dewribed in the safety analym report and C) te.ts or esperunents turnpleted under the pinviaun of 10 Cl it i

1 6 I'I l

Amendment No. 74 Br

CUC-CITIES' DPR-29 l

MINIMLH SMITT F>am:NO CHAnd CONDITICr> CF 04C UNIT (No Fuel in Sccen: Unit)

License Initial fuel Leading Cold Shutdewn er Abcve Cold Cat eerv er Durino :efuel'no

efuelin: Smutde-r Shutcown Senior C;erater License 2

I 1

Operator License 2

1 2

Rad. Prot. "an l

1 l

1 l

1 Non-Licensed (As Required) 1 l

2 Shi.ft Technical Advisor None Pe7Jired ibne Rac"Jired I

CCN0!i!CN OF SECCN3 UNIT (Cne Unit at Hot Shutdown er at Power)

License Initial Fuel Leading Col'! Shutdown or Above Cold Category or During Refueltr.g Refueling Shutconn Shutdo-n Senior

• Caerator License 2

2 2

C erator' License 3

2-3 Rad. Pret. Man I

1 l

1 l

1 1

N:n. License:

l 3+ (as Recutred) l 3

l 4

Shift Technical Advisor 1

1 1

b CCN3! TION OF SECOND UNIT (One Unit.a_t Cole Snutdo-n or Refueling Shutdown)

License Initial Fuel Leading Cold Shutd wn or Above Ccid Cate; cry or Durinc Refueltn:

efuelinc Snutde=n Shutdown Senior' C erater License 2

1 2

C; crater

• License 3

2 2

Rad. Pr:1. Man l

1 l

1 l

I

3. (Ag evuiredi 3

3 N:n-Licensec Shift Technical Advisor Ncne ReeJir#.

None Recraird 1

'Assu es each ine'vicual is licensed on each facility. During initial fuel loading or during refueling, One senior engineer (limited license) will supervise fuel handling.

f Shif: ::ew ce=positien =ay be less than the =ini=u: require =ents for a period of ti=e no to ex:ced 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order :o acco= eda e unexpe :ed absence of on duty shif: crev =e=bers previded i=ediate action is taken to restore the. shif: : ev ce=posi:icn to within the

~4 re-quire =ents of Table 6.2.2-1.

Amendment No. 74 FIGURE 6.1-3

e t> Etivg j

f Ig UNITED STATES g

NUCLEAR REGULATORY COMMISSION 3

y E

WASHINGTON, D. C. 20556 os

/

++***

COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE _

Amendment No. 67 License No. DPR-30 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated September 18, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in co.npliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; l

and i

E.

l'1e issuance of this amendment is in accordance; with 10 CFR Part j

Sl of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Speciff-cations as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-30 is hereby amended to read as follows:

3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 67, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

f 1;

1 1

4 i

2-3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY CO M ISSION I

_- )

& ~# p; 2 A ~' Thomas I. I polito Chief

.'~

Operating Reactors Branch #2 Division of Licensing

Attachment:

Cha.1ges to the Technical Specifications i;

Date of Issuance: August 21, 1 981 4

t I

l i

~

h

)

\\

i 4

,----c n,

l t

ATTACHMENT TO LICENS6 AMENDMENT NO. 67 q

FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 I

Revise the Appendix "A" Technical Specifications as follows:

Renove Replace 6.1-1 6.1-1 Figure 6.1-3 Figure 6.1-3 1

1 l

a s

,_-,.-,,.+.e,

,y.m,

,-.,..----c.,

m--

+.< -

e

1 i

i l

CUAD CITIES DPR-in 1

6.0 ADMINISTRATIVE CONTRO!.S g

6.1 ORGANIZATION, REVIEW, INVESTICATION, AND AtJDIT.

A. The Station Supermtendent shall luve overall full.ume responubihty for safe opersten of the faedity. Durms periods when the Station Supenntendent is usuvadable. he shall deuenste this responsibthty to an estabbshed alternate who satisfies the ANSI N18.1 of March d,1971 experie' ice requirements for plant manspr.

2 The corporate management which reistes to the operation of this station is shown m Figure 6.1 1.

C. The normal functional or;2nization for operation of the station shall be as shown in Figure 6.12. The shift manntrg for the station sha!! he shown m Figure 6.. 3. The individual fdling the ponnon of Admmistrative Assistant shall meet the minimum acceptable level for "Technisal afanager" n described in Section 4.'.4 of ANSI N18.l.1971.

A fire brigade of at least 5 members shall be mamtsmed on.ute at all timer. This excludes the shift crew nece:ssry for safe shutdown of the plant, and any personnel required forother essential functions dunng a tire emergency.

D. Qualificatians of the station manseement and operating staf f shall nneet minimum seceptable levels as desenbed in ANSI N18.1, " Selection and Traintr.g of Nue! car Power Plant Personnel". dated March 8,1971. The Rad / Chem Supervisor shall meet the requirements of radiation proteetton manager of Rerufstory Guide 1.8. 'ite Shif t Tecnnical Advisor shall have a bachelor's -'egem or equivalent in a scientific or enginecrirn discipline with nor'cific training in plant design, and response and analysis of the plant for transient and accidents.

E. Retraining and repla:ement traming of Station personnel shall be in accordance with ANSI N18.1."Si'ection and Training of Nuc! car Power P!snt Persormel",dsted March 8,1971.

A train! rig program for the fire brigade shall be maintamed under the direcuan of the Station Fire Marshal. and shall meet or ex:eed the requirements of Section 27 of the NFPA Code-1975 except that traming sessions shsil i

be at least quarterly.

(

F. Retraining shall be conducted at mtervals not exceeding 2 years.

G. The Review and Investigative Function and the Audit Funct:en of activities affecting quality dunng facdity opera.

ticas shall be constituted and have the responsibdities and auGontres outhned below:

1. The Supervisor of the Offsite Review and Invesugative Function shall be appointed by the Vice President of Construction. Production. Licensing and Environmental Alfstrs. The Audit Function shall be the responsibdity of the Manager of Qushty Assurance and shall be mdependent of operations.

a.

Offsite Review and Investigative Function De Supervisor of the Offsite Review and Invesugative Function shall:(1) provide directions for the review and investigatise function and appomt a semor partjipant to provide appropnate direction.(2) select each part:cipant for this function.(J) select a complement of more than one participant who collectively possess bsekground and qualificstions in the subject matter under review to provide com-prehensive interdisciplinary review coverace under this function.(4) tndependently review and approve the findings and recommendations developed by personnei performine the review and investigative function,(5) approve and report m a timely manner all findmus of noncompliance with NRC require.

ments to the Station Supe mtendent. Division Manager Nuclear Stations. Manager of Qushty Assurance, and the Vice Preudent of Construenon Production. Licensing and Environmental Atfstrs.

During periods when the Supervisor of 0ffsite Review and Invesugstive Funetton is unsysdsble, he sha;' designate this responubdity to an e;tsblished alter.ute.who sausfies the formal tramtng and ex.

pare :e requirements for the Supervisor of the Otfsite Review and Investigsttve Funcuan. The retponsibilities of the personnel performmg this function are stated below. The Offsite Review and +

Investagsuve Functmn All reuew:

1) The safety evatusuons fer i1) shanges to procedures, equipment, or systerm as dewribed m the safety analyus eeport and (2) t:sts or experiments completed under the provmon of 10 CFR

'1 Arnendrnent No. 67 6.1 1

?

7""

GUAD-CITIU DPR JO MINIMLH SMITT '.WSING CHARTt l.-

c CONDIT!0*l 0F C*dE UNIT (No Fuel in Secon: Unit)

[nitialFuelLeading Cold Shutcown or Above Cold License Cateeorv or Durine Refueltno

efuelin: Seutec="

Shutdown Senior Operator

, License 2

1 1

Operator License 2

1 2

Rad. Prot. Man l

1 l

1 l

1 Non-Licensed (As Required) 1 J

2 Shift Technical Advisor None Pecuired mne Recuired 1

CON 0!T10N OF SECOND UNIT (One Unit at Hot Shutdown or at Power)

License Initial Fuel Leading Cold Shutcown or Above Cold Cate; cry or During Refueling

cfueling Shutco n Shutco n Senior' Operator License 2

2 2

0;erator' License 3

2-3 l

1 i

l Rae. Prot. Man I

1 l

1 N:n-Licensee i

3+ (As Reevired) l 3*

l 4

Shift Technical Advisor 1

1 1

6 Coto!T10N OF SECOND UNii (One Unit.j_t Cold Snutcown or Refueling Shutdown)

License Initial Fuel Leading ~~Iold Shutde-n or Above Cold Cate;ory or During Refueltn; Refueline Shutdown Shutco-n Senior' 0:erator i

License 2

1 2

0;crator*

3 2

2 License Rad. Prot. Man l

1 l

1 l

I Non-Licensed 3+ fAs Secuiredl 3

3 Shift Technical Advisor None RecrJiraf.

None Recuired 1

' Assumes each indivicual is licensed on each facility. During initial fuel 1cading or during refueling, one senior engineer (limited license) will supervise fuel handling.

f Shif crew co=posi: ion =ay be less :han :he =ini=u= require =ents for a period of ti=e so: 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 acco==odate unexpected absence of on duty shif: crev me=bers provided i==ediate action is

aken to restore the shif: crew cc:posi:icn :o vi:hin the mini::r.:= re-quire =en:s of Table 6.2.2-1.

7 rasugrout_s