ML20101L104

Requests Approval of Encl Revised Changes to QA Program Descriptions,Per 920608 Discussions W/Nrc.Procedure Change Tracking & Trending Process,Specified in Proposed Change, Being Put Into Effect

ML20101L104
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	06/19/1992
From:	Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9207060257
Download: ML20101L104 (12)

Text

..

i ;

10CFR50.54(a)(3)(1) 1 i Pillt.ADELPillA El.ECTRIC COMPANY i NUCLEAR OROUP HEADQUARTERS 955-65 CilESTERHROOK HLVD.

WAYNE, PA 19087 5691 l (215) 640-6000 ,

June 19, 1992  :(

i Docket Nos. 50-277 NUCLEAR ENGINEERING & $0RVICf3 DtTARTMENT 50-278 50-352

50-353

{ License Nos. DPR-44

& DPR-56 4 NPF-39 1 NPF-85 ,

1 i

! I t -

j U.S. Nuclear Regulatory Commission 3

Attn Document Control Desk j washington, DC 20555 ,

Subject:

Peach bottoin Atomic Power Station, Unit 2 and 3  !

j Limerick Generating Station, Units 1 and 2 1

Request for Approval of a Change to the Quality  ?

l Assurance Program Descriptions l Supplemental Information i  !

l Gentlement i

1 Our letter dated December 13, 1991, requested approval of e enange j to the Quality Assurance (QA) Program Descriptions incorporated _in the j Updated Final Safety Analysis Reports (UFSARe) for Peach Bottom Atomic j Power Station (PBAPS), Units 2 and 3, and Limerick Generating Station  ;

! (LGS), Units 1 and 2. As a result of subsequent discussions with J.- -

i Caruso, NRC Region I, and NRC letters-dated January 27,_1992, we j submitted revised changes to the QA Program Descriptions by letter dated May 4, 1992. Discussions-principally covering our l self-assessment process were.then held with N. Blumberg and E.-Benner, NRC Region 1, on June 8, 1992, during which additional information was l requested. Accordingly, this letter-provides the requested information ,

and a revision to the changes to our QA Program Descriptions submitted l by our letter dated May 4, 1992. .The revised changes are provided'in l Attachments 1 and 2 for PBAPS and LGS respectively. The remaining i

marked-up UFSAR pages provided by our December 13, 1991 letter are I unaffected by these revised changes.

I During-the discussions held on June 8, 1992, the following documents were provided to Messrs. Blumberg and Benner.-  !

c. i The current station procedure governing the periodic procedure review process.

o E -

The station guideline gcVerning the self-assessment process.

'Of 0 -

Copies of letters from a number of other licensees (e.g.,

f4 South Carolina Electric and-Gas) requesting NRC approval to o o u w_., Aw qs gw a yoI in

_ _ _ . --- . - -- . . . . _._ . -- .- .. . - . .= , _

U.S. Nuclear Regulatory Commission June 19, 1992 i

' Document Control Desk Pago 2 i

doloto the commitment to perform periodic procedure reviews.

These licensee requests have boon approved by the NRC.

J A comparison of our proposed change and those submitted by the sample of other licensoos shows that the bases for the changes are effectively i the same. Differences betwoon the programs and processes that are identified as being offective in maintaining procedures current are duo j

< to differences in program or process titles only. For example, tho  ;

program specified in our proposed change as " Programs governing the i a

identification, documentation, and initiation of procedural improvements," results in obtaining the same end user feedback on procedures as the following programs identified in other licenseo requests that have boon approved by the NRC; plant personnel foodback, the simulator training program, plant operator feedback, and the surveillance test program.

The only difference between our proposed change and those of the j other licensees is that wo intend to rely on the self-assessment procean together with oversight by the Nuclear QA (NOA) organization

] instead of periodic NQA audits conducted specifically to assess the i offectiveness of programs and processes in maintaining procedures.

current. Self-assessment by each lino organization has becomo a part

of the normal conduct of operations within the Philadelphia Electric Company (PECo) Nuclear Group. As such, relying primarily on individual self-assessments as proposed hors ensures that the responsibility to 4

maintain procedures current is properly retained by the lin6

{ organizations that use the procedures. The self-assessment process is required by Nuclear Group policy and associated implomonting documents, and includes the requirement that lino organization self-assessments, including identified weaknesses, be documented and corrective actions be tracked to completion.

In addition, the self-assessment process includos validation by comparing the self-assessment findings with those of other groups or agencies such as the NRC and the PECo NQA organization, that conduct <

oversight activities. Furthermore, if one of these groups or agencies 1

identifies a concern that the lino organizations did not find as part of its self-assessment, the line organization is responsiblo for determining the reason the weakness was missed. Therefore, based on the above discussion, we are confident that our self-assessment procoas together with the oversight assessment of the procedure development i'

programs and processes by the NQA organization will be effectivo in maintaining the procedures that are now subjected to periodic reviews properly up-to-date.

During the June 8, 1992 discussions, the question of how procedures that appear to be used on a non-routine basis are maintained current, such as emergency operating procedures (EOPs), off-normal procedures (ONPs), procedures that implement the Emergency Plan, and

, other procedures that would be uced during a specific event, was raised. "Non-routine" oporating procedures (e.g., EOPs and ONPs) are in fact used routinely during the NRC required initial licensed operator training and the continuing licensed operator roqualification training programs. Similarly, Emergency Plan implementing procedures 4

, - . , , , . . . - --,, .~e - . ,. , - . . n,.. n,. . , , , , . . . , , , , .,n ~,.. - -,m -

U.S. Nuclear Regulatory Commission June 19, 1992 Document Control Doak Pago 3

]

i

and other procedures used to respond to an emergency are used during l periodic NRC required emergency drills and exercises. Such frequent

! usage of "non-routino" proceduros within the framework of the procedure

! development programs and processes specified in this proposed chango to i the QA Program Descriptions, has and will continuo to be offectivo in .

! identifying and implomonting nooded changes and enhancements to this j category of proceduros. Accordingly, the proposed changes to the PBAPS -

and LGS QA Program Descriptions have boon revised to specify the applicability of the proceduro development programs and processes to "non-routino" procedures.

}

j Finally, the procedure change tracking and trending process

specified in this proposed change is boing put in effect, and will i provide for the timely identification of the reason for procedure 4 changes. By tracking and trending the reason for procedure revisions, J we will be able to periodically evaluate this information and tako correctivo actions as necessary. Thoroforo, this process providos an l 4

additional means of ensuring that the procedure development programs and processos are offective in maintaining procedures current.

If you have any questions or need additional information, please contact us.

l l Very truly yours,

, 60 Y 4 G. J. Bock, Manager Licensing Section 1

cc T. T. Martin, Administrator, Region I, USNRC w/ attachments

J. J. Lyash, USNRC Senior Resident Inspector, PBAPS w/ attachments T. J. Kenny, USNRC Senior Resident Inspector, LGS w/ attachments l

1 1

i 4

, --a- -

- ,-r-,v .,,n . . . - , - -w- - - , ~ , - - - - - - - - - - - - , ~ ,- _--- - , , , e - - - , , -+- - - . .

i 0

l j l 1

l 5

l 1

4 1

1 1

1 I

l l ATTACHMENT 1 i Peach Bottom Atomic Power Station i

a d

I 1

l 1

i I

l I

l l

l

1 1

l -

/ - - 'N l ',

4 .PBAPS.

J s 1 .

The Materials Section and Purchasing Department shall only ,

17.2.4.7 process approved requisitions in accordance with PECo procurement procedure,s and policies.- . s: .

. e t .. ..

The Purchasing Department shall not citer the technical 1* 17.2.4.7.1 information or quality assurance re;eirteents on a re utsition . .~

of any procurement classificatien identified as QS, QV, QO cr

- lix item without, specifically requested prior, writun l

approval of the requisitioning organintica.

i 17.2.4.8 The procuremant document for QS and QV items shall include a provision for the right-of-access to ver.dcr f acilities for l j

i inspection or audit purposes. '

,1 f  !

3 1

17.2.4.9- . Procurement documents shall be caintained in acccrdance with

• Section 17.2.17.

• j .

f- Instructions, Procedur'es, and Drawines 17.2.5 ,

l-s .

17.2.5.1 Activities associated with the impittentitlen of the liuclear f Quality Assurance Program shall be described and acccmplished j

i

'in accordance with appropriate instructicas, procedures, and-

• INSEU A^ drawings.

• Administrative procedurts shall be STitten for l j i safety related activities and approved by the apprcpriate management. QA shall review and approved adctnistrnive l * '

~

i procedures. .

17.2.5.1.1 .PBAPS Administrative Procedures shall te written by the plant staff, reviewed by the PORC, approved by the Plant Manager or. ,

an appointed designec and the site Quality Manager - HQA, and distributed to predetermined personnel.

l

[ -

17.2.5.1.2 These Administrative Proceduris shall contain provisions which clearly delineate the sequence of actions (cr the preparation, review, approval, and control of activity implementing procedures, instructions and drtwir.gs. Exhibit XI delinettes*

the manner in which the criteria of 10Cf7.50, Appendix B,.are l

implemented for each plant activity. ,

0.11-27 .' Rev.9,07/91 2

Proposed ,

i

- - * - + ,e- .,e-m,.-,,.,,,,,,,g, ,, ,_ __

u.. :_ .. . . _ ~ _.

.' .'.. PBAPS APPEN0!X 17.2A REGULATORY GU10E5 AND ANSI STANDARDS NUCLEAR GROUP OPERATIONS PHASE OVALITY AS$URANCE 1294(10/26/73),

f PECo will follow the QA guidelines included in WAS; 1309(5/10/74) Guidance on Quality Assurance f Nuclear Power Plants"; " ASH l l

j Requirements During tt. Construction Phase .

S l

l i

and Procurement Phase of Nuclear Power Plan as described in this Appendix. __

I, l The Peach Bottom QA Program is described by the PSAP5 QA Plan.,

1 f

i j PEco has conductd an extensive review of the above alo_ ng with the Regulatory Guides The standards were and-Industry Standards. i al f

reviewed with respect to those activities occutring during the~c; o.

erat o

^

j phase that are comparable in natureThe and extent io'and recc.mendations l

related acti i .

occurring during initial design and construction.

l guidance of the Regulatory Guides ~and ANSI Standards wh j nuclear plant operations are incorporated in the P!APS QA Plan. ,

i Administrative and implementing procedures af fected by any rev l PBAPS QA Plan will be revised as required in accordance with A i

Procedures.

standards addressed by the Regulatory Guldts End ANSI

• tandards are excluded unless a! dressed separately.

i' 1.8 3/10/71 Persor.nal Selecticn and Training. Endorses- ,

1. Reculat_or L G_uide 1 ANSI N18.1 - 1971' ,

COMPLY 4

4 0.11-51 p g,g7jgg FOR INFORMATION ONLY a.

• * ' ' ' + - - , - , , , , , _ , , _ , , _

g

. c.

. . .PSAps j  ; .. N, ., '  : '.

.' - .  ? -

J 4 -

.:< 9 1;'.:. , .

l -

I e.

AH51 H45.2.4/ S ction 6.2.1, fouloment TestOlnstalled items reqvfring calibration are controlled through the preventive maintenance conputer tracking . system. Tags or labels are not affixed to the ites to indicate calibration status.

j *

4. Reculetory' Guide 1.33 - November'1972, Quality Anurance Program '

l liequirements (0pHtTen). - - - .  : . . - , , _ ,

! i i

FECo shall comply vith Regulatory Guide 1.33, 11/72, which endorses M5i

{ H45.2 - 1971 and ANSI H15.7 - 1972 exclusive of other dccuments referenced.

• l

! *IN5I?I 3 .

5. Reculatory Guide 1.37 - 3/16/73, QA Pequirteents Icr Cleaning of fluid Systems and Associated Components of Water-cooled NPPs. Endorses MSi i

N45.2.1 - 1973. .

t 8

Decontamination and cleanup of radioactive contaminated systems and i

) certponents are not included in the scope of this respense.

PEco shall comply with Regulatory Guide 1.37 - 3/16/73 and MSI h!.2.1 - -

i 1973 for those activities occurrino during the operational phase that era .

i

! - ccmparable in nature and extent to related activities cccurring during the -

initial design and construction phase except for the following alternate:

1

a. - ANSI H45.2.1, Section 3.?, Vater Ouality Recuirements - pH catsurements ,, .

l- ,

are ngt required.for conductivity values of less than or tqual to 1 3 '

! umho/cm. PEco utilizes pH limits of 5.2 to 8.6 at 25 C. vncerrtetti for CO2 and my apply conductivity measuratents*in place of totti dissolved .

solids. _

(

i~

6. Reculatory Guide 1.38 - 3/16/73, QA Requirements for Fackaging, Shippir.g, j Receiving, Storage and Handling of items for Water.ccoled HPPs. Enderses

AHS! H45.2.2 - 1972.

PEco .shall comply with Regulatory Guide 1.38,3/16/73, and MSI N4!.2.2 -

[

1972 for those activities occurring during the operational phase that tre comparable in nature and extent to relt'ed activities occurring during the initial design and construct.on phase acEpt for the following alternates

, .t j- a. ANSI H45.2.2, Paragraph 2.7, Classification of items PECo dor.s not classify items into the four (4) levels described in this Stande-d.

' However, the specific guidance and recomendations which are-

' appropriate to each class are applied to those items packaged, shipped, l . .

2 3 0.11-53

(

. U. ? .u d , , , , , ,, ,,

. gey, g, 07jg; G

• 4 --v.--w -v - ,w- e - w r 3,--y-.,- ,.,s.r.s v-gs,,a,--,r-s-~ev.sr 't-e-ww-+-y-e.. emer r-meg.+,-++mg3,. ..=,5 te y- nve g, me r -m- -ve -3%w +e www- - + -.'ws>=---w,,- -e. +e = eye v . - is*w, --e-

l l

Insert A

. I Programmatic controls and processes described in Item 4 of UFSAR 1 Appendix 17.2A are in place to assure that procedures are maintained current. These controls take the place of, and oliminate the need for scheduled periodic reviews and revisions.

Insert B Adds except for the following alternates

a. the following programmatic controls and processes are used to assure that procedures are current. These procedures include those that are used on a routine and non-routine (e.g., emergency operating procedures) basis. Non-routine procedures will be maintained current by the pr(grammatic controls and processes specified below since many of these procedures are_used frequently during NRC required licensea operator initial and continuing requalification training and during NRC required i emergency drills and exercises. These controls take the place of scheduled periodic reviews.

Plant modification process.

Amendments to the Technical Specifications.

Programs governing the identification, documentation, and initiation of procedural improvements.

Temporary procedure changes.

Nuclear Quality Assurance assessment activities.

In-House Event Investigation Program.

Operating Experience Assessment Program.

Vendor Manual Program.

Procedure change tracki_g and trending process.

Line organizations that have responsibility for procedures or procedure categories will perform biennial self-assessment of the appropriate components that comprise the procedural development program in accordance with established guidelines.

These self-assessments will provide a high degree of confidence that the programs and processes identified above are effective in maintaining procedures current. In addition, the Nuclear Quality Assurance (NOA) organization will assess the programs and proceases identified above as part of the NQA assessment function that includes audits and surveillances.

4

. i 1

l.

l 1 1 l

4 1

l j i i

i 4

i 1

ATTACHMENT 2 Limerick Generating Station 4

4 a

_ .. w-, , ~,--.,r p -.a..-. , ._ , , , ,,-. ,-, -- e. , , , , , _ . _ , , .-

'l E,

l 2-

. '.' :i.lf..

.= . . ...

is$d .. . . @ . . W.

S

. M f-l.y@@%..a . . ....-:.f?.2. @ e ..

. . . . .",. , . 1: . . r w~:e.',.14.- . . .. : ,. 1. 91, g . :,' ,. , . . . . .;. .

.( ,N18.

. , Q ** . . . . .

7- 19 7 6 / Mis m.3. 2, 3 c.:5.2.13.1, S ecticn, ;.; , . . ,., . -

]

17. ANSI {y'c:Procur ient and Docunent Control,.(second sentence) , - i

~- QA . Program requirenents ~ cr alternate' approved ,

nethods' will be used .to ensure cuality/ f Exa:aples t . ' "

i j

.of alternates f or isuppliers ' vithcut, CA' precrans 4

' include: raterial analysisj ssanle testing, in-j process ; inspection and nonitoring,,.and . design , " ' -

.' review by PECo. .

4

• Section 5.2.15, Revie ._

e ANSI N18. 7-197 6/ ANS 31, 2

18. l j

Aceroval and control of Trocedures - The frequen:y of review of plant procedures is discussed in UFSA?. l I

l, *I55IRT A - Section 13 5.*

i 3.7, Secticn 5.2.17, MISI NI B . 7-197 6/ANS 19.

Insoectionn - The results of inspections are net always subject to a f u ther evaluation. Fer evaluation beyond that -given bv i

example, Inspection-level personnel is not ncr: ally recuirai ~

for go/r}o-go and pass / fall type inspections. ,

20. MfSI N18.7-1976/A15 3.2, Section 5.3, .Preceratien -

_o f Instructions end Procedureg (last. sentence)

The clarification regarding energency naintenance i in Item 12, above, applies.

21., ANSI N18.7-197 6/ ANS 3.2, Section 5.3.10, Test'and

s '

l ,

...Insuection Procedures, (first prragraph) -

n.e clarification regarding test result Svaluatiens in j

j Iter. 19,.above, applies. ., ,

22'. ANSI 'N18.7-197 6/ mis 3.2, Secticn 5.3.10, Test and j

Inseection Procedures, (second paragraph, last These , procedural aspects -vill he sentence) -

l included when appropriate. For exanple,-"as-found i condition" is not applicable to all'. test and 3 inspection procedures. .

~

d. Reculatorv Guide 1.37, March 1973, " Quality Assurance Requirements for Cleaning of Fluid Systens and Associated +

• Components of Water-cooled Nuclear : Power ~P11nts." * - -

Endorses ANSI N45.2.1-1973.

}. .r .

l .

Decontamination ar.d citanup,of radioactively contaninated 4 systems and component's are not included in the scope ^of -

this response /

, .-f,',,(,;,:;

'. ..'.n.. '

- /g ,

. . . . . . . . . . v . .: .- .-7

. . . .~, ..- ..

f._....,

r. f . ,.

? top 0500 A

. . ' :lc = ,'. . ., ;' f ..

• l

. ;. ' g . ' , . * .

s.

1 . ,

. . ~ . * . . - **;

17.2.II-6  !

{

- M u '. . , . ..

e. .a. . ,.. 0:. n t,.r. h. ...A y . :.Y. . : ,W.

.. Las UTSAnL...v

.a n% 8 ' .a- .

e

.. v<,p8. . ' *.

. . . .w c .

53.5 JLANT_ PROCEDURES ,, ),* ..', , ,. s;f [.. . p,-

saf etv-related actihities performed by the ' plant staff .shall he

~

coverned by sritten and approved procedures of a' type appropriate to tne circumstances and activity, and shall be cadled out in -

accordance 'with those precedures'. *.. ..? Where app;cpriate fer .#

determining that important activities have been satisf acterily accomplished, quantitative or qualitative acceptance criteria shall be included. PCCo utilizes the operating experience gained at PSA?S Units 2 &3 (BWP, units similar to LGS) in the development cf the procedurcs.

As fully described below, PEco has in.pler.ented ANSI F18.7 (1976)/

. ' ANS 3.2, Section 5 as r. edified by NRC Regulatory Guide 1.33 (P.tv 2), paragraphs c.1 and c.5.b through c.5.j, as these docur.ents apply to 6perating staff activities,

• in the preparation, content, 1$E?.T 3 end control of procedures. l Secticns 33.5.1.1 through 13.5.1.25 -describe administrativa precedures. Many of these sections, describe hev varicus precedure types (such as naintenance procedures er preventive maintenanct

~

crocedures) are developed and controlled, yherets other sec'icns ,

' describe' an administrative process (such as purchasing)l -Enhss s tet e d---v t-h ervis c. in--the-c eebiens--whhch--d eet-ibe-hev V:.. '.;

. procedure-.-t-ypes-are-devekped-e+.d-ceMt:11:d, th: ;;;i:lic rr. :..

e4--the-procedures-wi-11-be--on = y::.r~hes40. N s:--th:t-Vill i:.

r-:#i4+wc4 #1.t-h-c 5, ear--f-recuency-are--pr+4d:d vith nti:n:1:= t:- 3 sqper4-thi s-.pec-6t+m.

E+ch..+f-the-r-at4onales-r.esec et 1 east-4*-p+r4- ;-- th puiti:n t-het-the-perre--passege-c4-t-be-is-nct-suf u-- c.% a a fiaiett runn t: ::vi: u._

V:

preeecare f c-r tSequach. -. . 6-------..c u.

. -- .----w---

yeee er -equenc-y-does--ncet-pr+v4dc a basis-t-+r--th::1:ctier :: :

veee-c . Something-nustwccu -dur4+.g-the-peesep cf tb: thot +aM iskc-the-rev4ew-or-r-evic hrr-:4 *. pMeedur : r-+;tr:; ht: ::th: ta tek . :t- sheeld-be-not+i--t't t ce ntre11-0 24A+a ! :~;i Faent ::

susterr ned4-1-icationo-r+swit-i->-the r: vie Of-- Spr44cth p:+ced:::s f'or-th e pceentia-1-e4f-ee-t-c ! the-se64fec t h .. ~; dfit her, 5 ttader d--pra c t4c e s-s e g &+difig-- r 71:U: Ed I E p E O ~. IC - 3 0 NrtM'a n_nac sul14tirehale.r: 2nd %t4ser, '"!0 f sc==t: =f nduct-ey--deen nento-t-hct ir =00rMMd by th! *pe " '" ?""d** N -

Assessr.ett !'repr* -and--f+r* 0,5 h cO&N7 th'- ih4.t-St:ff tr-S kn--place and--o. ,e--pr.+cedu r e: to ts--r tvi:Utd nf :?ised-+t-eppropriate in r-elati:n t th VieU :f ID6i--l##Edet+

-d eeuwirts .

?:opesd -

..r ..

13.5-1 .

4 l'- ' u -

__.-______.m_._______.-._m_

1 J

Insort A j Adds "except for the following altornativo:

a) programmatic controls and processos described in UFSAR section 13.5 are tjod to assure that proceduros are current. Thoso j controls take the place of scheduled periodic revicws."

I 1

1 Insert B j "The following programmatic controls and processes are in place to assure that procedures are maintained current. These procedures

include those that are used on a routine and non-routine (e.g.,

i omorgency operating procedures) basis. Non-routine procedures will be maintained current by the programmatic controls and processes specified below sinco many of these procedures.are used frequently during NRC required licensed operator initf al and continuing requalification training and during NRC required emergency drills and

exorcises.- These controls take the place of, and eliminate the need

] for, scheduled periodic reviews and revisions.

Plant modification process.

, Amendments to the Technical Specifications.

! Programs governing the identification, documentation, and

initiatiois of procedural improvements.

Temporary procedure changes.

Nuclear Quality Assurance assessment activities.

In-House Event Investigation Program.

operating Experience Assessment Program.

Vendor Manual Program.

Proceduro change tracking and trending process.

Line organizations that have re.sponsibility for procedures or procedure categories will perform biennial self-assessments of the appropriate components that comprise the procedural oevelopment program in accordance with established guidelines.

These self-assessments will provide a high degro9 of confidence that the programs and processes identified above are offective in i maintaining procedures current. In addition, the Nuclear Quality Assurance (NQA) organization will assess the programs and processes identified above as part of the NQA assessment function.

that includes audits and surveillances.

i d

a 4

ev ,y r.-r- - ,.m. .-- - - - - - ..

e...r.v. ,. w c- a,-. m- - * - , --,r.,-e w - - - . . --+---e---e, - - --- - -.-r --., . - --