Text

Proposed Tech Specs Re Administrative Controls
	ML20029B175
Person / Time
Site:	Prairie Island
Issue date:	02/25/1991
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20029B172	List: ML20029B171; ML20029B173; ML20029B175;
References
	NUDOCS 9103060088
	Download: ML20029B175 (34)
	v • d • e

_ .m._ . - . . _ . . . . . . _ _ . _ . _ . _ _ . . . . _ . -

4

' 6 i

Exhibit B i ,

Prairie island Nuclear Generating Plant

License Amendment Request Dated February 25, 1991 Proposed Changes Marked up on Existing Technical Specification Pages Exhibit B consists of the existin6 Technical Specification pages with the proposed changes written on those pages. The existing pages affected by this License Amendment Request are listed below: i l' Ate s TS xiti i i TS.6.1 1 TS.6.1 2 Table TS,6.1 1 Figure TS.6.1 1 Figure TS.6.1-2 TS.6,2 1 TS.6.2 3 TS.6.2 4 TS 6.2 5

.. TS.6.2 6 l'

-TS.6.4+1 TS,6.5-4 TS.6.745.

TS,6.7 6 h

i

, r!ER* 2888R uggg g, o em .

l .-

L . . - . a ._._,,,.-.__,_.__. _ ._ - .__ _ .._,.-... _. _ .....a...,.. _-_a._ . . _ . . . , . . _ . , _ - . . _ , , , , _ _ , . , . , , . . . . .

~ . _ . . ...n-_-.. --.w - . . . . . ~ . . _ - - _ - . . . - - . - - - . .-. - - - - .

l l

TS xiii !

" E'? 9 : 2/12/"^

, l 1

l' APPENDIX A TECHNICAL SPECIFICATIONS

- LIST OF FICltRES v

TS FICtmE IIILE 2.1 1 Safety Limits, Reactor Core, Thermal and Hydraulic Two Loop j_ Operation 3.1 1 Unit 1 and Unit 2 Reactor Coolant System Heacup Limitations 3.1 2 Unit 1 and Unit 2 Reactor Coolant System Cooldown Limitations 3.1 3 - DOSE EQUIVALDiT I 131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant i

= '

Specific Activity >1.0 uCi/ gram DOSE EQUIVALENT I 131 3.9 1- Prairie Island Nuclear Generating Planc Site Boundary for Liquid

- Effluents 3.9-2 Prairie Island Nuclear Generating Plant Site Boundary for Caseous Effluents ,

3.10 l' Required Shutdown Margin Vs Reactor Boron Concentration

./. -,\

N-f 4.4-1 . Shield Building Design In Leakage Rate 6,4 4 "SP C:q:rst 0:;en! eti:n:1 ?eletirnA!; te 0-!!te Oper?ti ;;

^ ;;;;i: 11;;:

4,4 4 P::iri: ::1:2d "u:1::: c::::::in; P12 : N : !:::1 0:;:n1:::i:r _

f:: On-Sit: Op::: ting c::up t

D 4 6 4;

e i

b

. s 4

,<---+rr- ,,33- . E +--m y .< ,ye,.,,-w., .-r ,ww v., m..w,,.,.,..,-,y ..,,,--w.-%., ,,,wr--i.w.., ,ew...--wwww-,m --,......,e-w--e*-.ve., -

IS.6.1-1

-e.. t j:f g -

6.0 ADMINISTitATIVE CONTROLS 6.1 ORGANI"ATION A. T5: %: ":n;;; S: th: : :::11 full-tin :::it: :::p n;itility I,wsert A J f:: ::fe :;::: tier cf the freility >>:in; ;:: icd: d :- 05: " le.n ;

v:n ;:: 4a.-eav ril:512 'e e-j dele;ne th!: ::: pent!S!!itr ::

eth:: peli!ied supervice-" pe- ernel.

v g, ,.t. u...t... e..... u, .m.... ..,.. 4.. 4...$ .....n... ..a . w hsed__ [.!..!~._.~1'.._._!_!_!.'1_6_'._E,p.I

r. . _ _ < .

~ i'_ i."_ i_ . ~ !_ t li."'!_ !_ ~ ? i_ .E,i_. I_ ' _F. l_ '. i. li. ', '

C. ~5: '::: ! nal : ;:nirstic" for ;erati n f th: :1:n 7 :l l-+e-

;h: '- Tigur: T!.5.'_-2

. nd: ' Plant Staff:

1. Each en duty shift shall be composed of at- least the m.inimum shif t crew composition shown on Table TS.6.1-1.

2. For each reactor that contains fuelt a licensed operator in the control room.

- 3. At least two licensed operators shall be present in the control room during a reactor startup, a scheduled reactor shutdown, and during recovery from a reactor trip. Thesa operators are in addition to those required for the other reactor.

4 An-individual qualified in radiation protection procedures shall be on site when fuel is in a reactor.

5. All refueling operations shall be directly supervised by a licensed Senior Reactor Operator or a Senior Resetor Operator f,imited to Fuel Handling who has no other concurrent respons-ibilities during this operation.

6. .\ fire brigade of at least five members shall be maintained i on site-at all timos.* The fire brigade shall not include the six members of the minimum shif t crew for safe shutdown of the V.7 " reactors.TAe, in tyt&q),( op r.llons manager) Mm. plant MahA3meni respon$i We. .for +(g overa,l( su.pervh. ion of PkA. plant operabtus geog shad be. OrMerry licer5<a .< bra , currext ucm . /

Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accomodate unexpected absence of Fire Brigade membera provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

^ ___

N= ---

s

8. A t le..n st c na. member o f _plad uanagemd helQ a cu rrr4 '

Sem:or.' Lek c eroJoe e Lwse shna Le. ^ a s s 1 pud to Hu plavt(

a Jon opo.rdios ye ar3) .

growp ate na;eus tfla&rm. ~ t 6<hasn a.u(atptotim&

A ko rotding sid fL , -~ -

]a..

[ ~

1

m The plant manager she de responsible for overall unit safe

[lnStrt A operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. The plant manager shall delegate in writing the succession to this responsioility during his absence. The plant manager has the

, responcibility for the rire protection program. __ f

[ B.~ Onsite and Of f sitin Organizations Onsite and offsite organizations shall be established for plant Insert B operation and corporate management. The onstte and offsite organizations shall include the positions responsible for activities

( affecting plant safety.

1. 1.ines of authority, responsibility and communD ation shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the forrn of orpnization charts, functional descriptions of departmental responsibilities and relationships, j

and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in corporate and plant procedures and Operational Quality Assurance plan.

2. There shall be an individual executive position (corporate officer) in the offsite organization having corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the plant to ensure nuclear safety.

3. There shall be an individual management position (plant manager) in the onsite organization having responsibility for overall unit safe operation and shall have control over those ons!te resources necessary for safe operation and maintenance of the plant.

( 4. The individuals who train the operating staff-and those who carry T out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence I

from operating pressures.

- ~ #

k

/

s

i IS.6.1 ;

G 6.I.C,7. wn -

breetcha nay D. Each member of the plant staff sha 1 meet or >xceed the minimum qualifica.

tions of A!;S! !!10.1 1971 for compa ble posi ions, except for ( ) the N t.eee.46+A M /adiatien frotectiothwho sha~1 meet or exceed the qualifica-tiens of Regulatory Guide 1.B. September 1 75, and (2) the /hift T e a m l Ac. who shall have a bachelors degree or equivalent in a scientific or engineering discipline with specific tta sing in plant design, and re-sponse and analysis of the plant for er sients and accidents, and (3) the h a i N p d m d a Plaa /perationsPwho shall meet the requirements of A!!SI !;18.1 1971, except that !;RC license requirements are as specified in iTF"U !! '. 2 The training program shall be under the direction of a designated nember of tierthern States Power management.

E. A trainin6 program for the fire brigade shall be maintained under the direction of a designated member of !;orthern States Power management.

This program shall meet the requiren>ents of Section 27 of the !!TPA Code -

1976 with the exception of training scheduling. Pire brigade training i shall be scheduled as set forth in the training program,

p. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions; e.g.,

senior reactor operators, reactor operators, health phycicists, auiliary operators, and key maintenance personnel. Procedures sball include the followingprovisionQ

1. Adequate shif t coverage shall be maintained without routine heavy no

)op ureofovertim@the objective shall be to have operating personnel vork a A 1-- 9 :_g 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week while the plant is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown !

for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed: i 1

a. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight excluding shift turnover time,

b. Overtime should be limited for all nuclear plant staff personnel so that total work time does not exceed 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 84 hov.rs in any seven day period, all excluding shift turnover time. Individuals should not be required to work more than 15 consecutive days without two consecutive days off,

c. A break of at least eight hours including shif t turnover time should be allowed between work periods,

d. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

e, nif t T -2 ch - i c 21 ' "i r " ' "T ' ' 2 w,1 S h i f : Emergency Coordinator (SEC) on site rest time periods shall not be considered hours worked when determining the total work time for which the abov mitations apply,

~

- ,m t \*I

TABLE T3.6.1-1 NININUN SilIFT CREW CDNPOSITION (Note 1 en,d 1)

~

CATEGORY BOT 11 UNITS IN c)LD SIRITDOWN ONE UNIT IN 0111s SIIt1TDOWN BOTil UNITS ABOVE 0)LD OR REfifELING SIIUTDOWN GR RERIELING SIRITIMUN AND SlitlTtxuti ONE UNIT ABUVE 0)LD SliUTDOWN No. Licensed Senior 2 (Note 2) 2 (Notes 2, 4) 2 (Note 4) f Operators (LS0)

Tots! Ho. Licensed 4 4 5 Ope ra t or s (LSO & LO)

Total No. Licensed & 6 7 8 Unlicensed Operators I

[ilft 9 9 -lee! '8-!-er O I 1 rnanafer hlcte 5)

NOTES:

1. Sinift crew composition may be one less than the minimum requirements for a period of time not to exceed two hours in order to accommodate an uneapected absence of one duty sliit t l crew member provided immediate act ion is taken to restore the shif t crew compoeition to wi t ta in the minismia requirement s specified.

2. Does not include the licensed Senior Reactor Operator, or Senior Reactor Operator Limited to Fuel llandlir.g. supervising refueling operatons. M a

3. Each LSO and LO shall be licensed on each unit. U" U

4. One LSO shall be in the control room at all times when a reactor is ab9 ve cold shutdown. IC'- o The sK.fl.

5.

Sec pr -

. Tecknical Aav.sc< [$-

m ._

4#we.E_M.O._m,,. a__ wk.Aa*.- m. mmamiaadd _w ams,am,&64A_Am.,M4.A4 4.jp_ & .4.4 wJ4.h,,4h h Mww o_ AwdAng3_.J M ,A hA D ae4M_ h h 3Maa m4dhs,3,g_M A 1C Man zM.- 34 J s A A D

s T10ure 75.0.4-1 YE: ~1 '!:$.

I1 l!.! -

-! 1-3

]!:

i 1: s r;:i e

1 hl- - - - - s:i 3

!=

a w '

1 I

N l I- -

ll l l.!!H.i =

l i

8" I t s I !

I E

I l

cEl

N I l 56 g ,. e l !!!

yI!,

I X I"f "'I E- I!

.]

9 -

ljI' i I"!

~$

lg g..

6 l u

1

EE I

I

& I I .

lc '. *

- N gir

[f:*

mai _

- go u

l-l .

i :

5 1

I I r L ;

i 5

" . i

!]

i" EjQ=

. li =

g I* i $lI s

I

_ i cg : g e______. --

33

,g!

! 3 Eji il 'l lg l

i!

t MGURE TS .6.1-2 Pr" C: , i , , i ';

f a, N -

i3e .

o 5 4

W W"9t sER-

" -j-6lI -

eIsI

\ g. [ 5 IO OV"

5 E ilse E5 s!I , B lN EllI i 5!(B gs assgg y [ I..

g ,p g a flg g

. nJ

,i set f "Er y /[

g s B !!!

95

- B g* -

i.,an - =g 2

E g = e is b, *

W8

~

k~ fe ) [Inii ,g $ Ikh f./g gg gIl !!

si i: h gh

_ il g;e!m-l .

s .: :e gg fl g*.! a! _ .

i ss!.

llg! sas is :lisil3 o i

. [s.

el!

S l -

o

!sisruss.it as E.

- Sh,.- + y

h- $

s. c a

$l , a _

6e -

L J s: x Jils 1

8 5

is i!"

e.g a

s lsi e

n!j

"'Iais lelr s

i mirag s ela.

He !5 gs , : es a 5-tvj B8 ie h t

l a K rrEi- <

5!

~

hh ersa d

w g4 r!$

5 e,

85f5 $"sik i gi r ei !

75.6.2-1 Pr: ~ 2 : :':5 :55 6.2 Review and Audit Organizational unies for the review and audit of f acility operations shall be constituted and havo the responsibilities and authorities outlined below:

"A . Safety Audit Comai t '. e e (SAC)

The Safety Acitt Committee provides the independent review of plant operations from a nuclear safety standpoint. Audits of plant operation are conducted under the cognizance of the SAC.

1. Membership

a. The SAC shall co . .

. ve (5) persons, corpate officte

b. The SAC ch raan alfTelhn~1S rep sentative, not having line res nsibility for plant opera on, appointed by the "i;; ?::_id::: M;;i::: C::::::i:r. Other SAC members shall f be appointed by the ..__ .._______ ______ _________ or by l such other person as ha may designate. The Chairman shall appoint a Vice Chairman from the SAC membership to act in his absence.

c. No more than two members of the SAC shall be from groups holding line responsibility for operation of the plant,

d. A SAC member may appoint an alternate to serve in his absence, with concurrence of the Chairman. No more than one alternate shall serve on the SAC at any one time. The alternate member shall have voting rights.

2. Qualifications

a. The SAC members should collectively have the capability

- required to. review activities in the following areas nuclear power plant operations, nuclear engineering, chemistry and radiochemistry, metallurgy instrumentation and control, radiological' safety, mechanical and electrical engineering, quality assurance practices, and other appro-priate fields associated with the unique characteristics '

of the nuclear power plant.

9

T3.6.2-3

. .T! ? ; - / ! / "J

l. f. Invsstigation of all Reportable Events and events requiring Special '

j. Reports to the Commission.

t

g. Revisions to the racility Emergency Plan Tacility Security Plan, and the i Tire Protection Program.

h. Operations Committee minutes to determine if matters considered by that Committee insolve unreviewed or unresolved safety questions.

a

1. Other nuclear safety matters referred to the SAC by the Operations .

Committee, plant managament or company management. .

j. All recognized indications of an unanticipated deficiency in some aspect

,. of design or operation of safety-related structures systams, or components.

k. Re

,4$ecification ports of special 6.3. inspections and audits conducted in accordance with

, 1. Changes to the offsite Dosa calculation Manual (0DCM).

s.- Review of investigative reports of unplanned releases of radioactive material to the environs.

6. Audit - The operation of the nuclear power plant shall be audited formally under the coguisance of the 3AC to assure scle facility operation.

a, Audits of selected aspects of plant operation as delineated in Paragraph 4.4 of ANSI N18.7-1972, shall be performed with a frequency commensurate '

with their nuclear safecy significance and in a manner to assure that an-audit of all nuclear safety-ralated activities is completed within a period of evo years. The audits shall be performed in accordance with appropriate written instructions and procedures.

L. Audits of aspects of plant -radioattive ef fluent treatment and radio-logical environmental monitoring shall be performed as follove:

1. Implementation of the offsite Dese Calculation Manual at least once Svery two years.

2. Implementation of the Process Control Program for solidificatien of radioactive vastes at least once every evo years.

3.- The Radiological Environmental Monitoring Program and the results thereof, including quality controls,-at least once every year.

c. Periodic review of the audit program should be performed by the SAC at-least twice a year to assure its adequacy. -~ - - ~ ~

( 0!Poca(L o , test

d. Written reports of the audits shall be reviewed by the "12: ":::id- : I

rl:2r ? - r2 1:1. by the SAC at a scheduled seating, and by memoers of management having responsibility in the araes audited.

2 I

J

TS.6.2-=

EE" $1 2f 2 'E3

7. Authority M4 e t:r '! ' 211- 2 T:n5 2 t i e:. l The SAC shall be advisory to the\

8. Records -

ce.r u.inutes shall tie prepared ar d retained for all scheduled meetings of the Cafety Audit Co =:ti t t t e e , *he minutes shall be distributed within one month of the meeting to theD1:::ter cf " :1:2r :ener*+i n, n: C: w+4 u r. ger " :1::: ?12nu, each member of the SAC and others designated by l

the Chr.irman. There shall be a formal approval of the minutes.

9. Procedures A vritten charter for the SAC shall be prepared that containst

a. Subjects within the purview of the group.

b. Responsibility and authority of the group.

c. *echanisms for convening meetings,

d. Provisions for use of specialists or subgroups,

e. Authority to obtain access to the nuclear power plant operating record files and operating personnel vnen assigned audit functions.

f. Requirements for distribution of reports and minutes prepared by the group 3 others in the NSP organization.

l

l C [8.'.6 .,2,- 5

m. .. _ ,..

, r .n .t.

B. Operations Committee (0C)

1. Membership f E3k

-=

kdfj The Operations Committee shall consist of at le as t sir. (6 )kl members drawn from the key supervisors of the onsite staf f.

E sert C > The flant )(anager shall serve as Chairman of the OC and shall appoint a +e- Ch aitanan f e4e-th OC _:25 ehl; :: :t in his

- - ""* dlay T a t.t Q S

.. Meeting Frequency The Operations Committee will meet on call by the Chairman or as requested by individual me'abers and at least monthly.

I' 9"Of"" ma Mber e kip A majority of the : rn::: r:d ::c, including the Chairman es "L %:L- cr 4 Responsibilities - The following subjects shall be reviewed by the Operations Committaet

a. Proposed tests and experiments and their results.

b. Modifications to plant systems or equipment as described in the Updated Safety Analysis Report and having nuclear safety significance or which involve. an unreviewed safety question as defined in Paragraph 50.59 (c), Part 50 Title 10, Code of Federal Regulations,

c. Proposals which would ef fect permanent changes to normal and emergency operating procedures and any other proposed changes or procedures that will af fset nuclear safety as determined by the giant )(anage r.

d. Proposed changes to the Technical Specifications or operating lice ns e s .

e. All reporter'. or suspected violations of Technical Specifica-tions, orarating license req'airements, administrative procedures, operating procedures. Rasults of investigations, includins evaluation and recommendations to prevnnt recurrence vill be reported in writing to the "i:: " ::id::: " ;1;;r .

l

'----" ^and to the Chairinan of the Saf ety Audit Connittee.

Corporade o kicer ~

s - -

nSefk O The key supervisors include, at least, the following positions:

plant manager, operations manager, maintenance manager, radiation protection roanager, and engineering supervisors.

Alternates to the regular members shall be de;ignated in writing by the Chairman to serve on a temporary basis. No recre than two I alternates shall participate as voting members of the Operations Committee at any one titte.

e n

l I

b d

I avb., . ,n-m---,, e-,,,w.,. ,,-,,n,_www.,,,,l--,, n.,- ,.,-., --,n n ,~n-,-n ,--- , . . . - - - , . , - -

TS.6.2-6

c- ",_!=-

ti

f. Investigations of all Reportable Events and events requiring Special Reports to the Commission,

p. Drills on energency procedures (including plant evacuation) and adequacy of communic 5 tion with offsite support groups.

h. All procedures required by these _ Technical Specifications, including implementing procedures of the Imergency Plan, and the Security Plan (except as exempted in Section 5.5..F). shall be reviewed initially l and periodically with a frequency commensurate with their safety significance but at an interval of not more than two years,

i. Special reviews and investigations, as reqvssted by the Saf ety Audit Comeittee.

j. Review of investigative reports of unplanned releases of radioactive matersal to the environs.

k. All changes to the Process Control Program (PCP) and the Of f site Dose Calculation Manuni (ODCM). ,

5. Authority TheCCshallbeadvisorytothe,[lant,panager. In the event of a disagreementbetweentherecommendationsoftheOCandthe)flant,[anager, the course determined by the,flant )(anager to be the more conservative vill be followed. A vritten summary of the disagreement will be sent

. to the ^ cr:1 M2nscer 'N ele'" "l'"t e and the Chairman of the SAC f or ~

~

review.

r corporoh, Officcf

6. Records- _ _ - - -

Minutes shall b e recorded for all meetings of the OC and shall identify all-documentary material reviewed. -The minutes shall be distributed to each member of the 0C, the Chairman-and each member of the Safety Audit Committee , theEC:n=r:1 Man:ger -Nuolear F12nte and others designated by the OC Chairman er Y h: Chai r n.

7. Procedures A written charter for the OC shall be prepared that contains:

a. Responsibility and authority of-the group

b. Content and method of submission of presentations to the Operations Committee

c. Mechanism for scheduling meetings

d. Provision for meeting agenda l

l

d

' . 4 TS.6.4-1

-n!" 15 *!:S!Si p ._ ,_ _

6.4 I SATETT LIMIT VIOLATICN C orP o mb _- OIOcer If a jTfety Limit

exceeded, the resetor shall be shut own and the Commission shall e notified immediately. It_shall also e promptly reported to the M: rrel M : ;;: "c le : "12::: ar.d the C airman of the Safety Audit Commaittee, or thsir designated alternates. A safety limit violation report shall be prepared. This report shall esc ribe (1) applicable circumstances preceding the violation, ( ) effects of $he violation upon facility components, systems or structu es, and (3) the basis for corrective action taken to preclude recurren e. The report shall be reviewed by the Operations Committee. The a fety limit viola-tion report shall be submitted to the Commission. the.!::::: M:::;;

and the Saf ety Audit Committee within two weeks of th4' event.

Operation shall not be resumed until authorized by the Nuclear Regulatory Cos. mission.

4

.f'

- -,-,a__, ., _ . _ _ . .

TS.6.5-4 REV 80 4/18/88 E. Offsite Dose Criculation Manual (ODCM)

The ODCM shall be approved by the Commission prior to initial implementation, Changes to the ODCS shall satisfy the following requirements:

1. Shall be submitted to the Commission with the Semi Annual Radio-active Effluent Report for the period in which the change (s) were made effective. This submittal shall contain:

a. sufficiently detailed information to totally support thn rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s).

b. a determinatiot. that the change will not reduce the accuracy or reliability,of dor.e calculations or setpoint determinations, and

c. documentation of the fact that the chango has been reviewed and found acceptable by the Operations Committes.

2. Shall become effective upon review and acceptance by the Operations Committee.

F. Security Frocedures shall be developed to implement the requirements of the Security Plan and the Security Contingency Plan, These implement-in5 procedures, with the exception of thosa non safety related procedures which govern work ae.vities exclusively applicable to or performed by security personnel, shall be reviewed by the opera-tions Committee and approved by a member of plant management designatedbythe/lant/anager. Security procedures not reviewed by the Operations Committee shall be reviewed and approved by the Sup : cicer, /ecurity d S:-ice:

C. Temporary Changes to Procedure .s - % s u per visor Temporary changes to Operations Committee reviewed procedures described in A,B,C.D,E and F above, which do not change the intent of_the original procedure may be made with the concurrence of two membe n of the unit management staff, at least one of whom holds a Seni'a Reactor operator License. Such changes shall be documented, reviewed by the Operations; Committee and approved by a

=e~ w e of plant mana5ement designated by the [lant [anager within er ) nth.

Tegorary changes to security procedures noc reviewed by the l Operations Committee shall be reviewed by two (2) individuals knowledgeable in the area affected by the procedure.

__ _ _ _ _ _ . _ . _ _ - . -- . _ _ _ _ = _ . . _ - _ _ _ . . _ _

TS.6.7 5

-RtW - M 2 /11, '; 1-XN NP-77 57 (A), XN NF 77 57, Supplement 1 (A), " Exxon Nuclear Power Distribution Control for Pressurized 'a'ater Reactors Phase II", May, 1981

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and cransient and accident analysis limits) of the safety analysis are met,

d. The CORE OPERATINC LIMITS, REPORT, including any mid cycle revisions or supplements thereto, shall be supplied upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Rogional Administrator and Resident Inspector.

B. REPORTABLE EVENTS The following actions shall be taken for REPORTAELE EVENTS:

a. The Commission shall be notified by a report submitted pursuant to the requirements of Section 50,73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the Operations Committee and the results of this review shall be submitted to the Safety Audit Committee and the Vic: Pccaiden "u c 1 c a r-Ce nc ra t i<m. .

O C A h 6, O h E i c e.(

I 1

l TS.6.7 6 REV 03 2/11/91 l 1

C. Environmental Reports The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:

1. Annuni Radiation Environmental Monitorinz Report (a) Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendar year shall be submitted prior to May 1 of each year.

(b) The Annual Radiation En'vironmental Monitoring Reports shall include summaries, interpre:tations, and an analysis of trends of td9r9pequits of the radiological environmental surveillan,gel3acpvities fo, the report period, including a comparison withTpreoperation,J studies, operai.onal controls (as appropriate), anu previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses tequired by Specification 4,10.B.1. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

(c) The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated retalts in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be subcitted as soon as possible in a supplementary report.

(d) The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results-of licensees participation in the Interlaboratory Comparison Program, required by Specification 4.10.C.1.

2. Environmental Specini Reports (a) When radioactivity levels in samples exceed limits specified in Table 4.10-3, an Environmental Special Report shall be submitted within 30 days from-the end of the affected calendar quarter. For certain cases involving long analysis tire, determination of quarterly averages may extend beyond the 30 day period. In these cases the potential for exceeding the quarterly linits will be reported within the 30 day period to be followed by the Environmental Special Report as soon as practicable.

.,, - . _ - _ . _ _ _ . _ _ ._.._._.-.-_.m. ..- . . _ _ _ . _ _ . . _ . _ - . . _ . . . _ _ _ . . . .- . _ . _ _ _ .

O ,

Exhibit C Prairie Island Nuclear Generating Plant

~ License Amendment-Request Dated February 25, 1991 REVISED TECHNICAL SPECIPICATION PAGES

~ Exhibit C consists of revised pages for the Prairie Island Nuclear Generating Plant Technical Specifications with the proposed changes incorporated as listed below:

Paces _

t TS-xiii TS.6.1 1 i

.TS.6.1 2 TS.6.1 3 TABLE TS.6,1-1 TS.6.2-1 TS.6.2 3 TS 6.2-4 TS.6.2 5 TS 6.2 6 ,

TS.6.4 1 TS 6.5 4 TS,6.7 5 TS.6.7 6 1;. -e i

i

-- w. -- U r , w,' g- , - + . , - y ,',w..,

TS xiii i

APPENDIX A TECHNICAL SPECIFICATIONS LIST OF FIGURES TS FICURE TJ,ILE -

2.1 1 Safety Limits, Reactor Core, Thermal and Hydraulic Two Loop Operation 3.1-1 Unit 1 and Unit 2 Reactor Coolant System Heatup Licitations [

3.1-2 Unit 1 and Unit 2 Reactor Coolant System Cooldown Limitations 3.1 3 DOSE EQUIVALENT I 131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERFLAL POWER with the Primary Coolant Specific Activity >1.0 uCi/ gram DOSE EQUIVALENT I 131 3.9 1 Prairie Island Nuclear Generating Plant Site Boundary for Liquid Effluents 3.9 2 Prairie Island Nuclear Generating Plant Site Boundary for Gaseous Effluents !

3.10 1- Required Shutdown Margin Vs Reactor Boron Concentration 4.4 1 - Shield Building Design In Leakage Rate t

1 e

1 i

. . . . . ~ - - _ _ . _ . - . - - . _ - - ,. - - - - - .

1 TS.6.1-1 I

6.0 ADMINISTRATIVE CONTROLS }

6,1 Organization The plant manager shall be responsible for overall unit safe A.

operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. The plant manager shall delegate in writing the succession to this responsibility during his absence. The plant manager has the responsibility for the Fire Protection Program.

B. Onsite and Offsite Organizations Onsite and offsite organizations shall be established for pit.nt

, operation and corporate management. The onsite and offsite organizations shall include the positions' responsible for activities affecting plant safety, s

1. Lines of authority, responsibility and communication shall be estab-lished and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descri-ptions of departmental responsiblities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in corporate and plant procedures and the Operational Quality Assurance Plan.

2. There shall be an-individual' executive position (corporate officer) in the vir ite organization having corporate responsibility for overall plant nuclear- safety and shall take any reasures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the plant to ensure nuclear safety.

3. There shall be an individual management position (plant manager) in the onsite organization having rosponsibility for overall unit' safe operation and who shall have control over those-onsite resources necessary for safe operation and maintenance of the plant.

4.. Ele individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to

~

'the appropriate-onsite manager; however, they shall have sufficic~nt F organizational freedom to ensure their independence from operating pressures.

C. Plant Staff: ,

1. Each on duty shift shall be composed of at least the minimum shift-crew composition shovn on Table TS.6.1 1-.

2. For each reactor that contains fuel: a licensed operator in the control room.

l .-

E . - - .

TS.6.1 2 3 .- At least two_ licensed operators shall be present in the control room during a reactor startup, a scheduled reactor.

shutdown, and during recovery from a reactor trip. These operators are in addition to those required for the other reactor.

4, An individual qualified in radiation protection procedures shall be on site when fuel la in a reactor.

5. All refueling operations shall be directly supervised by a licensed Senior Reactor Operator or a Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respons-ibilities during this operation.

6, A fire brigade of at least five members shall he maintained on site at all times.* The fire brigade shall not include the six members of the minimum shif t crew for safe shutdown of the reactors.

7. The individual (operations manager) from_ plant management responsible for the overall supervision of the plant operations group shall be formerly licensed or hold a current license.

8. At least one member of plant mancgement holding a current Senior Reactor Operator license shall be assigned to the plant operations Broup on a long term basis.(approximately two years). This individual shall not be assigned to a rotating shaft. .

D. Each member of-the plant staff shall meet or exceed the minimum qualifications of ANSI _N18.1 19711for comparable positions, except for (1) the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guido 1.8, September 1975, and (2) the shift manager who shall have 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, and-(3) the operations manager who shal1 meet the - l-requirements of ANSI N18.1 1971,_ except that URC license requirements are as'specified in Specification 6.1.C.7. The l.

training program shall be under the direction of a desionated member of Northern States Power management.

Fire Brigade composition may be less than the minimum requirements for a period of time not to' exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements

TS.6.1 3 E. A training program for the fire brigade shall be maintained under the direction of a designated member of Northern States Power management.

This program shall meet the requiremen:s of Section 27 of the NFPA Code -

1976 with the exception of training scheduling. Fire brigade training shall be scheduled as set forth in the training program.

F. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions; e.g.,

senior reactor operatoru, reactor operators, health physicists, auxiliary operatcrs, and key maintenance personnel. Procedures shall include the following provisions: l

1. Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

a. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight excluding shift turnover time,

b. Overtime should be limited for all nuclear plant staff personnel so that total work time does not exceed 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months in any seven day period, all excluding shift turnover time. Individuals should not be required to work more than 15 consecutive days without two consecutive days off,

c. A break of at least eight hours including shift turnover time should be allowed between work periods,

d. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift,

e. Shift Emergency Coordinator (SEC) on site rest time periods shall l not be considered as hours worked when determining the total work time for which the above limitations apply. l

W TABLE TS.6.1-1 MINIMUM SHIFT CREW COMPOSITION (Note 1 and 3)

CATEGORY BOTH UNITS IN COLD SHUTDOWN ONE UNIT IN COLD SHUTDOWN BOTH UNITS ABOVE COIE OR REFUELING SHUTDOWN OR REFUELING SHUTDOWN AND SHUTIXNN I ONE UNIT ABOVE COLD SHUTDOWN No. Licensed Senior 2-(Note 2) 2 (Notes 2, 4) 2 (Note 4)

Operators (LSO) '

Total No. Licensed 4 4 5 Operators.(LSO & LO).

Total No. Licensed & 6 7 8 Uni.icensed Operators L shift manager (Note 5) 0 1 i l ,

NOTES-

1. Shift crew composition may be one less than the minimum requirements for a period of time not to exceed two hours in order to accommodate an unexpected absence of one duty shift crew member provided immediate action is taken to restore the shift crew composition to ,

within the minimum. requirements specified.

2. Does not ine'lude the licensed Senior Reactor Operator, or Senior Reactor Operator Limited to Fuel Handling, supervising refueling operations.

~5

3. Each LSO and LO,shall be licensed on each unit. $i E

4 One'LSO shall'be in the control room at all times when a reactor is above cold shutdown. g

5. The shift manager performs the functions of the Shift Technical Advisor.

l-'

t

)

_ . . 4 - _ _- _ , _ . _ _ _ _ _ _ _ _ ._

1 TS.6.2 1 6.2 Review-and Audit Organizational units for the review and audit of facility operations shall be constituted and have the responsibilities and authorities outlined below:

A. Safety Aud!t Committee (SAC)

The Safety Audit Committee provides the independent review of plant operations from a nuclear safety standpoint. Audits of plant operation are conducted under the cognizance of the SAC.

1. Membership

a. The SAC shall consist of at least five (5) persons,

b. The SAC chairman shall be an NSp representative, not having line responsibility for plant operation, appointed by the corporate officer. Other SAC members shall be appointed by the corporate officer or by such other person as he may designate. The Chairman shall appoint a Vice Chairman from the SAC membership to act in his absence.

c. No more than two members of the SAC shall be from groups holding line responsibility for operation of the plant.

d. A SAC member may appoint an alternate to serve in his absence, with concurrence of the Chairman. No more than one alternate shall serve on the SAC at any one time. The alternate member shall have voting rights.

2. Qualifications

, a. Tie SAC members'should collectively'have the capability l required to review activities'in the following areas:

nuclear power plant operations, nuclear engineering, chemistry and radiochemistry, metallurgy, instrumentation and control, radiological safety, mechanical and electrical engineering, quality assurance practices, and other appro-priate fields associated with the unique characteristics of the nuclear power plant, l'

1:

l-

i TS.6.2 3

f. Investigation of all Reportable Events and events requiring Special Reports to the Commission,

g. Revisions to the Facility Emergency Plan, Facility Security Plan, and the Fire Protection Program,

h. operations Committee minutes to determine if matters considered by that Committee involve unreviewed or unresolved safety questions.

J. Other nuclear safety matters referred to_ the SAC by the Operations committee, plant management or company management.

J. -All recognized indications of an unanticipated _ deficiency in some aspect-of design or operation of safety-related structures systems, or components,

k. Reports of'special inspections and audits conducted in accordance with Specification 6.3. l

1. Changes co-the Offsite Dose Calculation Manual (ODCM).

m. Review:of investigative reports of unplanned releases of- radioactive material to'the environs.

6. Audit . The ' operation of the nuclear power plant shall be audited formally under the cognizance of the SAC to assure safe facility operation,

a. A'udits of selected aspects of plant operation, as delineated in Paragraph 4.4 of ANSI N18.7-1972, shall be performed with a frequency commensurate with.their nuclear safety significance and in a manner to assure that an audit of all nuclear safety related activities is completed within a period of two years. The audits-shall be performed in accordance with approprit.te written. instructions and procedures,

b. . Audits of-aspects of plant radioactive effluent _ treatment and radio --

logical environmental monitoring shall-be performed as.follows:

1. Implementation.of the offsite Dose Calculation Manual at least once every two years.

! 2. Implementation of the Process Control Program for solidification of.

E radioactive-wastes at-least once_every two years, u

.3. The. Radiological Environmental Monitoring Irogram and the results__

thereof, including quality controls, at least once overy year,

c. Periodic review of the audit program should be performed by the SAC at Icast twice a year to assure its adequacy.

d. Written reports of the audits shall be reviewed by the corporate officer, by the SAC at a scheduled meeting, and by members of management having responsibility in the areas audited.

l p-

TS 6.2 4

7. Authority The-SAC shall be advisory to the corporate officer,

8. Records Minutes shall be prepared and retained for tell schedulod' meetings of the Safety Audit Committee. The minutes shall be distributed within one

' month of the meeting to the corporate officer, each member of the SAC l and others designated by the Chairman, There shall be a formal approval of the minutes, j t

9. Procedures A written charter for the SAC shall be prepared that contains

a. Subjects within the purview of the group,

b. Responsibility and authority of the group.

c. Mechanisms for convening meetings, i

d. Provisions for une of specialists or subgroups. !

e. Authority to obtain access to the nuclear power plant operating record files and operating personnel when assigned audit functions,

f. Requirements' for distribution of reports and minutes prepared by the group to others in the NSP organization, j

l

~

~ + -- - -

, , --. .____.__a

_ . . . , _ _ _ . _ . _ _.__.m. .- ..~ . _ . _ - - _ . .. _ . _ . _ _ _ . _ _ . _ _ . .

TS.6.2-5 B. Operations Committee-(00)

1. -Membership-The Operations Committee shall consist of at least six (6) regular members drawn from the key supervisors of the onsite staff. The key supervisors include, at least, the following positions: plant manager, oparations. manager, maintenance manager, radiation protection manager, and engineering supervisors.

Alternates to the regular members shall be designated in writing by the Chairman to serve on a temporary basis. No more than two alternates shall participate as voting members of the Operations

-Committee at any one time, The plant manager shall serve as Chairman of the OC and shall appoint a regular member to act as Chairman in his absence.

2. Meeting Frequency ,

The Operations Committee will meet on call by the Chairman or as requested by individual members and at least monthly.

3. Quorum A majority of _ the membership, including the Chairman.

4 Responsibilities The following subjects shall be reviewed by the Operations Committee:

a. Proposed. tests and experiments and their results, b, Modifications to plant systems or equipment as described in the Updated Safety Analysis. Report and having nuclear cafety significance or which involve an untsviewed safety question-as defined in Paragraph 50.59 (c), Part 50. Titic 10, Code--of Federal Regulations.

c. Proposals which would effect permanent changes to normal -

and emergency: operating procedures and any other proposed changes or procedures that will affect nuclear safety as i determined by the plant manager. I

d. Proposed changes to the Technical Specifications or operating licenses.

c. All reported or suspected violations of Technical Specifica-tions,-operating license requirements, administrative procedures, operating procedures. Results of investigations, including evaluation and recommendations to prevent recurrence will be reported in writing to the corporate officer and to the Chairman of the Safety Audit Committee, i

-4 TS 6.2 6

f. Investigations of all Reportable Events and events requiring Special i Reports to.the Commission.

g, Drills on emergency procedures (including plant evacuation) and adequacy of communication with offsite support groups.

h. All procedures required by these Technical Specifications, including implementing procedures of the Emergency Plan, and the Security Plan (except as exempted in Section 6.5.P), shall be reviewed initially and periodically with a frequency commensurate with their safety significance but at an interval of not more than two years,

i. Special reviews and investigations, as requested by the Safery Audit Committee.

J. Review of investigative reports of unplanned releases of radioactive material to the environs.

k. All changes to the Process Control Program (PCP) and the Offsite Dose Calculation Manual (ODCM).

S. Authority

- The OC shall be advisory to the plant manager. In the event of a disagreement between the recommendations of the OC and the plant manager, the course determined by the plant manager to be the more conservative will be followed. A written summary of the disagreement will be sent to the corporate officer and the Chairman of the SAC for review. l

6. Records Minutes shall be recorded for all meetings of the Oc and shall identify all documentary material reviewed. The minutes shall be distributed to each member of the OC, the Chairman and each member of the Safety Audit Committee, the corporate officer and others-designated by the OC Chairman.

7. Procedures A written charter for the OC shall be prepared that contains:

a. Responsibility and authority of the group

b. Content and method of submission of presentations to the Operations Committee

c. Mechanism for scheduling meetings

d. Provision for meeting. agenda Y

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

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

.._ _ . - . _ . - ~ _ . . - _ . _ _ _ . _ . _ _ _ _ . _ _ _ . _ _ _ _ _ _ . _ . _ . . _ _ _ . _ . _ . _ _

e TS.6.4 1

. 6.4 SAFETY LIMIT VI0lATION If a Safety Limit is exceeded, the reactor shall be sh..t down and the l Commission shall be notified immediately. It shall also be promptly reported to the corporate officer and the Chairman of the Safety Audit l Committee, or their designated alternates. A safety limit violation report shall be prepared. This report shall describe (1) applicabic circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) the basis for corrective action taken to preclude recurrence. The report shall be reviewed by the Operations Committee. The safety limit violation i report shall be submitted to the Commission, the corporate officer I and the Safety Audit Committee within two weeks of the event.

Operation shall not be resumed until authorized by the Nuclear Regulatory Commission.

i.

i l.

I l

TS,6,5 4 E, Offsite Dose Calculation Manual (ODCM)

The ODCM shall be approved by the Commission prior to initial implementation, Changes to the ODCM shall satisfy the following requirements:

l'. Shall be submitted to the Commission with the Semi Annual Radio-active Effluent Report for the period in which the change (s) were made effective. This submittal shall contain:

a, sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental-information. Information submitted should consist of a package of thos.e pages of the ODCM to be changed with each page numbered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s).

b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c, documentation of the fact that the change has been reviewed and found acceptable by the Operations Committee,

2. Shall become effective upon review and acceptance by the Operations Committee, F. Security Procedures shall be developed to implement the requirements of the Security Plan and the Security Contingency Plan. These implement-ing procedures, with the exception of those non safety related procedures which govern work activities exclusively applicable to or performed by security personnel, shall be reviewed by the Opera-tions Committee and approved by a member of plant management designated by the plant manager, Security procedures not reviewed l by the Operations Committee shall be reviewed and approved by the-security supervisor, !_

C. Temporary Changes to Procedures

-Temporary changes to Operations Committee reviewed procedures

. described in A,B,C,D,E and F above, which do not change the intent of the original-procedure may be made-with the concurrence of two members of the unit management staff, at least one of whom holds a Senior Reactor Operator License, Such changes shall be documented, reviewed by the Operations Committee and approved by a-member of plant management designated by the plant managcr within l one month.

Temporary changes to security procedures not reviewed by the Operations Committee shall be reviewed by two (2) individuals knowledgeable in the area affected by the procedure.

TS.6.7 5 XN NP 77-57 (A), XN EF 77 57, Supplewant 1 (A),

Exxon a Nuc1 car Power Distribution Control for Pressurized Water Reactors Phase 11", May, 1981

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thetmal mechenical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met,

d. The CORE OPERATINC LIMITS REPORT, including any mid cycle revisions or supplements thereto, shall be supplied upon icsuance, for each reload cycle, to the NRC Document Control Desk with copics to the Regional Administrator and Resident Inspector.

B. REPORTABLE EVENTS The folivaing actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified by a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT chall be reviewed by the Operations Committee and the results of this review shall be submitted to the Safety Audit Committee and the corporate officer, s

e TS.6.7 6 C. Environmental Reports The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:

1. Annuni Radiation Environmental Monitoring Report (a) Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendar yeer shall be submitted prior to May 1 of each year.

(b) The Annual Radiation Environnental Monitoring Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a l comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 4.10.B.1. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

(c) The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

(d) The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory Comparison Program, required by Specification 4.10.C.1.

l

2. Environmental Special Renorts i

(a) When radioactivity levels in samples exceed limits specified in Table 4.10 3, an Environmental Special Report shall be submitted within 30 days from the end of the affected calendar quarter. For certain cases involving long analysis time, determination of quarterly averages may extend beyond the 30 day period. In these cases the potential for exceeding the quarterly limits will be reported within the 30 day period to be followed by the Environmental Special Report as soon as practicable.

1

_ _ _ _

ML20029B175

Text

Navigation menu

Search