Text

Revised Pages of Rev 25 of Illinois Power Nuclear Program QA Manual
	ML20086U283
Person / Time
Site:	Clinton
Issue date:	07/20/1995
From:	; ILLINOIS POWER CO.
To:	;
Shared Package
ML20086U280	List: ML20086U283; U-602469, Forwards Response to NRC Comments Re Rev 25 of Illinois Power Nuclear Program QA Manual, Submitted on 950126 & Proposed Changes Submitted on 950217.Revised Pages of Nuclear Program QA Manual & Revised Pages of USAR Also Encl;
References
	NUDOCS 9508040030
	Download: ML20086U283 (47)
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I 4c to U-602469 Page1of10'

.' This attachment contains the following replacement pages for IP Nuclear Program Quality 1

! Assurance Manual, Revision 25:

Chapter 4, page 3 of 3.

Chapter 7, page 4 of 4 -

Chapter 8, pages 1 of 3,2 of 3, and 3 of 3 (The total number ofpages for.

Chapter 8 was 2 in the January 26 submittal. Adding the inadvertently deleted -

section increased the total pages for Chapter 8 from 2 to 3.)

i Chapter 18, pages 1 of 4,2 of 4,3 of 4, and 4 of 4 (Adding audit frequencies to l

Chapter 18 increased the total number of pages in that chapter from 3 to 4. The audit frequencies appear on pages 1 of 4 and 2 of 4.)

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.i 9508o4003o 950720 PDR ADOCK 05000461 P_

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Attachm nt 2 to U-602469

'lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 4 b.

Review purchase orders / contracts for quality.

assurance program requirements.

4.3.4.

Nuclear Station Encineerina-a.

Specify technical and quality requirements for materials, parts, components or services for CPS.

b.

Review and approve design changes that result from procurements.

c.

Provide specifications for procured materials, parts, components or services for CPS.

4.3.5 Nuclear Assessment a.

Evaluate supplier technical ability and approve supplier quality assurance program. (CCT 8347) b.

Conduct audits and surveillances of the procurement document control program to ensure compliance with the requirements.of this chapter.

(CCT 8348) l

)

1 1

l PAGE 3

of 3

REVISION 25

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Attachment.2 l

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to U-602469 Page 3;of.10

.l ILLINOIS POWER NUCLEAR PROGRAM i

QUALITY ASSURANCE MANUAL Chapter 7'

{

J 7.3.3.

-Nuclear-Suonort Services 1

-l a.

Implement l procedures. for. the receiving, storing, and issuing of-purchased items.

b.

Qualifiedi inspectors. perform required receipt inspection -of Laaterials 'or equipment prio.r to l

issuing the material'or equipment for operation.

j j!

'7.3.4 Purchasina and Material Control i

Perform reviews of suppliers' capabilities'to meet 1

a.

commercial terms and conditions prior to release

.l

-of the purchase order or contract.

b.

Verify the suppliers are listed. on the Qualified Suppliers List as required.

l i

7.3.5 Nuclear' Assessment l

a.

Perform source.

surveillances and audits of-

{

suppliers' quality assurance

programs,

,or establish alternate controls, prior to release of.

the initial purchase order or award of contract.

l (CCT 8354)

{

b.

Perform surveillances and audits at suppliers' facilities to verify compliance.with the quality l

and technical.

requirements of procurement j

documents.

l 1

c.

Conduct surveillances and audits of the control' l

measures applied to purchased material,. equipment, and-services to ensure compliance 'with~ the requirements of this chapter.

'I d.

Perform and document source surveillances at the suppliers' -facilities to verify that procured.

'l Items or services 'are. in compliance with..the requirements of the procurement. documents.

(CCT-

-l 7997) a.

Maintain the -Qualified ' Suppliers-List current-

-(

based on the results of. the surveillances mand j

audits.

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Page. 4 of 4

REVISION 25 z 1

..sn : >

to U-602469 ILLINOIS POWER NUCLEAR PROGRAY ' ' 1 QUALITY ASSURANCE MANUAL CHAPTER s

IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS 8.1 PURPOSE / SCOPE To define the requirements and responsibilities for a program of identification and control. of materials, parts, and components such that traceability is assured and the use of incorrect or defective items is prevented.

8.2 DESCRIPTION

~ ~ ~

~Meisufesi' have been established which provide for the identification and control of materials, parts, and components to assure that traceability is provided and the use of incorrect of defective items is prevented. (CCT 8171)

These measures include the following:

a.

Procurement documents specify appropriate identification to be applied to purchased items.

(CCT 8294) b.

An inventory control system is employed for the

receipt, storage or

stocking, and issue of materials, parts, and components.

c.

The identity of materials, parts, and components is either on the items or on records traceable to i

them.

When physical marking is employed, the marking is

clear, unambiguous, indelible, and applied in such a manner as to not be detrimental to the intended function of the item. (CCT 8294) d.

Markings are not obliterated or hidden by treatment or coatings unless other means of identification are substituted.

e.

When codes, standards, or specifications require traceability of materials, parts, or components to specific inspection or test records, the program is designed to provide such traceability.

f.

When employed, identification is transferred to f

each part of an item prior to its being subdivided.

k Page _L of 3

REVISION 25

to U-602469 Page 5 of 10 ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 8 Materials,

parts, and components shall have appropriate identifying designation (such as serial number, part number, heat number, etc.) in order to provide traceability to each item to inspection and test records and/or reports.

Where physical identification of an item is either impractical or insufficient, physical separation or additional procedural controls are employed. (CCT 8295)

When installed material or equipment is removed for maintenance,

repair, or modification, control measures are implemented to ensure proper identification markings and traceability throughout its processing.

During fabrication, assembly, installation, and shipping activities at a

supplier's

facility, the supplier conducts verification inspections and is responsible for identification and control of materials, parts, and components in accordance with the requirements of the IP purchase order. (CCT 8296)

Material, parts, and components are identified and controlled during fabrication, maintenance and modification activities performed at CPS.

Material, parts, and components are also identified and controlled during receipt and storage at CPS.

The IP department responsible for supplier work at CPS is responsible for ensuring that identification and control of materials, parts, and components by the supplier are in accordance with applicable procedures.

Surveillances and audits are conducted to assure that identification and control of materials, parts, and components are in compliance with program requirements. (CCT 8298) 8.3 EXEPONSIBILITIES 8.3.1 Nuclear Procram Departments a.

The Nuclear Program Departments responsible for supplier work at CPS are responsible for ensuring that identification and control of materials, parts and components by the supplier are in accordance with applicable procedures.

8.3.2 CPS Plant Staff a.

Implement a

program that provides for the identification and control of materials, parts and components used at CPS.

8.3.3.

Nuclear Succort Services a.

Implement an inventory control system for the 1

I identification and control of materials, parts and components.

1 Page 2

of 3

REVISION 25

Attechm:nt 2 to U-602469 I

l' age 6 of 10

.lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 8 i

8.3.4 Nuclear Assessment a.

Conduct surveillances and audits of the identification and control of items to ensure compliance with program requirements.

(CCT 8298) t 4

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of 3

REVISION 25

Attechment 2 to U-602469 Paga 7 of 10 ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 18 4

AUDITS 18.1 PURPOSE / SCOPE To define the requirements and responsibilities for implementing the program of planned and periodic audits which verify compliance with quality assurance programs and determine effectiveness in meeting program objectives.

18.2 DESCRIPTION

IP's Quality Assurance program includes provisions for planned and periodic audits designed to verify compliance with the requirements of the IP Nuclear Quality Assurance Program and to determine the effectiveness in implementing the program objectives.

(CCT 8022)

The audit program provides for the following:

a.

Provisions are made for both internal and external

~

audits. (CCT 8009) b.

Audits include the full range of activities within the scope of the IP Nuclear Quality Assurance Program.

These audits shall encompass:

i 1.

The conformance of unit operation to provisions contained within the Technical Specifications and.

applicable license I

conditions at least once per 24 months; f

I 2.

The performance, training and qualifications

{

of unit staff at least once per 24 months; 3.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 12 months; 4.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10CFR Part 50, at least once per 24 months; 5.

The Emergency Plan and implementing' procedures at least once per 12 months; Page _l_ of 4

REVISION 25 t

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-Attachment 2 i

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'to U-602469 Page 8 of 10'

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" QUALITY ASSURANCE MANUALj Chapter.18

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!!LLINOIS POWER NUCLEAR PROGRAM-L 6..

The Security Plan and implementing procedures-at least once per.12 months.

7.

Anyl other area; of unit operation considered.

j appropriate

'by the NRAG

.or.

the Vice i

' President.

8.

The. fire. protection programmatic controls j

including

.the-implementing procedures at' least once per 24 months by qualified licensee QA personnel.

9.

The fire protection _ equipment and program j

implementation shall be performed at least

.i once per 12 months utilizing either. qualified 6

offsite licensee fire protection engineer (s) or an outside independent fire ' protection consultant.

i 10.

An inspection and audit of the

-fire protection and loss prevention-program shall be performed by an outside qualified fire consultant at intervals no. greater than 36 months.

11.

The.

radiological environmental monitoring program and the results thereof at least once per 12 months.

l 12.

The OFFSITE-DOSE CALCULATION' MANUAL and' implementing. procedures'at least once per 24 l'

months.

4 13.

The PROCESS' CONTROL PROGRAM and' implementing procedures for solidification 'of radioactive wastes at'least once per 24-months.

14.

The performance of activities required by the ~

Quality Assurance Program-to meet the criteria of Regulatory Guide 4. 1 5,. December i

1977, at least once per 12 months.

f Additionally, program audits include-interface-between. IP audited organizations and other-affected organizations and USAR commitments. (CCT' 8105) l c.

Provisions are made for regularly scheduling

{

audits based upon the status and importance of-the

)

activities. (CCT 8106)

.]

d.

A qualification system is established for auditing personnel.

Independent certifying agencies may be Page,_2_ of 4

REVISION 25 l

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Attachr.:nt 2~

3 to U-602469 I

ILONOIS POWER NUCLEAR' PROGRAM Page t or 10

. QUALITY ASSURANCE MANUAL'-

Chapter 18 used. for.. the development and administration of lead auditor examinations.- (ccT 24358) e.

Personnel conducting audits do not have any direct.'

l responsibilities for the activities being audited.

(CCT 8010) f.

The audit team leader is charged with instructing l

the other ~ members during audit preparation and

?

performance.. Personnel conducting s audits shall have.

training and/or

-experience.

with the activities being audited. (CCT 8010) g.

Written audit plans. are developed -which. identify-

)

the scope, requirements, activities to be audited,

- 1 organizations

involved, applicable documents, schedule and written procedures or checklists - to,

be used for each audit.

j i

h.

Audit results are documented, reports' are j

generated and retained.

i.

Audit reports are distributed.to responsible i

management of the auditing organization'and to the J

appropriate managerial ' level:.of the organization having responsibility for the area or activity audited. (CCT 24357) j.

Appropriate. corrective action is ' developed.

(CCT 8011) k..

Follow-up action' (including' re-audit) is'taken to verify that corrective action has been completed and the resolution documented..(CCT 8011)

Audits are initiated as early in the life of the activity as practicable consistent with the. schedule for = accomplishing the activity to assure timely implementation of the quality assurance requirements.- Audits may be augmented ' at any time based-on l

)

i recommendations from the Nuclear Review and.. Audit Group, or Nuclear Program.-personnel as the scope of work and other requirements for auditing an activity change.

l Audited organizations are required. to review and provide 1 timely written response to audit-findings stating corrective action taken-or planned to correct deficient areas and prevent-j recurrence. (CCT 8299)

Audit program requirements'are imposed on i

suppliers by appropriate contract or procurement documents.. _(CCT

.l 8300)

Reports of internal audits are forwarded to. the : Nuclear Review

'and Audit Group and the Independent Safety Engineering Group for Page 3

of 4

REVISION'

'25

p C'

LAttachm1nt 2 g,

to U-602469'-

Page 10 of 10 lLLINOIS POWER NUCLEAR PROGRAM t QUALITY ASSURANCE MANUAL-LChapter-.18

. program evaluation. (CCT 8301)

IP. Management obtains independent;

, audits of'the Nuclear ~ Assessment organization. (CCTL8302) 18.3 RESPONSIBILITIES

~18.3.1 Nuclear Procram Departments a.

Maintain a

program for determining and implementing corrective actions to audits.

18.3.2.

Nuclear Review and Audit GrouD a.

Review reports of internal audits for program evaluation.

18.3.3 Nuclear Assessment a.

Implement an internal audit program and audit each IP organization performing activities within the scope of the quality assurance program to verify.

that the requirements of this manual are being met. (CCT 8022) b.

Implement an external audit program and audit suppliers performing quality related activities to verify ' compliance with the supplier's - respective quality assurance:

programs, contract, specifications and requirements, as defined on the purchase requisition. (CCT 8009) c.

Coordinate for the Vice President, the performance l of independent audits.of the Nuclear Assessment organization.

(CCT 8302) d.

Implement a program for evaluating:the adequacy of corrective actions to audits. (CCT 8011) e.

Independent Safety Engineering Group review reports of internal audits for program evaluation.

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of 4

REVISION 25

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a to U-602469 '

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-Page1 of1' j

This attachment responds to the NRC reviewer's comments regarding the proposed changes to the CPS position on conformance to Regulatory Guides (RGs) 1.33 and 1.144 as discussed in the submittal dated February 17,1995 (IP letter.U-602398).

(1)

The submittal requests approval for proposed changes in audit frequencies l

(RG 1.133) and in the need for root cause evaluation and follow up of -

i' audit findings (RG 1.144). The NRC reviewer requested that the proposed USAR pages be submitted for NRC review. IP agreed to provide those proposed pages. See Attachment 4 of this letter for proposed USAR pages 1.8-48a and 1.8-171.

(2)

The frequencies of unit activity audits performed under the cognizance of the Nuclear Review and Audit Group were relocated from the Technical Specifications to the Operational Requirements Manual (ORM) when the Improved Technical Specifications (ITS) were approved and implemented.

l The NRC approved the relocation of the audit activities to the ORM at the time ofITS approval. The NRC reviewer requested that the audit -

i frequencies be located in the IP Nuclear Program Quality Assurance Manual. IP evaluated this request and concluded that relocating the audit j

frequencies to the IP Nuclear Program Quality Assurance Manual would be

]

clearer to all parties. IP has changed Chapter 18 of the manual to include.

the audit frequencies. See Attachment 2 of this letter for changed pages -

1 of 4,2.of 4,3 of 4, and 4 of 4, Chapter 18.

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l This attachment contains the following replacement pages for the CPS USAll i

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t 3.2-15 l,

e 3.2-27' l

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Attechment 4 to U-602469 ag2 f5 CPS-USAR Revision Beaulatorv Guide 1.33. Rev. 2 (February 1978) (Cont'd) 7)

With regard to Section 5.2.15 of ANSI N18.7-1976 titled Review Acoroval and Control of Procedures: Programmatic controls for periodic reviews of procedures specify that applicable plant procedures will be reviewed following an unusual incident such as an accident, an unexpected plant transient, significant operator error, or equipment malfunction and following any modification to a system.

Non-routine procedures (such as emergency operating procedures, off-normal procedures, and emergency plan implementing procedures) shall be reviewed every two years and revised as appropriate.

Routine plant procedures that have not been used for two years shall be reviewed prior to use.

At least every two years, Nuclear Assessment, as part of the routine audit process, will audit plant procedures to verify the review and revision process is being implemented effectively.

Procedure changes and reviews as a result of industry feedback (such as NRC generic letters, information notices, and bulletins; or, as a result of industry significant operating event reports) shall satisfy the requirements of a procedure review.

A revision of a procedure constitutes a procedure review.

8)

Reference:

paragraphs C.4.a, C.4.b, C.4.c -- The following audit frequencies will be followed:

a.

Audits of the results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety -- 12 months.

b.

Audits of the conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions --

24 months.

c.

Audits of the performance, training and qualifications of the unit staff -- 24 months.

I USAR Chanter /Section - 12.5.3, 13, 17.2, ORM 6.8.1c.

l 1.8-48a to U-602469 CPS-USAR Revision Page 3 of 5 4

Reculatorv Guide 1.144. Rev. 1 (Sentember 1980)

Auditing of Quality Assurance Programs for Nuclear i

Power Plants Proiect Position - Comply, with the following exception:

1)

Reference ANSI N.45.2.12, Section 4.3.2, Audit Process, and 4.5, Follow-up.

The auditing organization will determine which program deficiencies and nonconformances (based upon significance) require root cause evaluation and/or follow-up by the auditing organization.

Corrective action implementation for deficiencies or nonconformances of lower significance is verified through the site corrective action program and the normal audit and surveillance process.

USAR Subsection - 17.2 l

1.8-171

7 7e '

^

CPS-USAR ReviCion 6i May 1995 TABLE 3.2-1 (Cont'd)

QUALITY QUALITY GROUP ASSURANCE SAFETYs SEISMIC CLASSI-REQUIRE-ELECTRICAL

'~

PRINCIPAL COMPONENTSfa1 CLASSfb)

CATEGORYfc)

FICATIONfd1 MENTSfel COMMENTS LOCATIONfs1 CLASSIPICATIONft1 IX.

Process Radiation Monitors 1.

Electric modules, main steamline, containment building fuel transfer vent plenum, containsment building exhaust, fuel.

building exhaust, and main control-room intake monitors I

N/A B

(w)

N/A 1E 2.

Cables with safety-function I

N/A B

N/A 1E 1

l X+ RBR. System (sections 5.4.7, 6.2.2, 6.3, and 6.5.2) (v) 1.

Heat exchangers, shell side 2

I B

B A

N/A 2.

Heat exchangers, tube-side 3-I C

B A

N/A 3.

Piping within outboard reactor coolant.

pressure boundary isolation valves 1

l'-

A B

(g)

A,C N/A

4., Piping, beyond outboard reactor coolant pressure boundary isolation valves 2

I' B

B-(g)

A,C' N/A-5.

Pumps 7'

I B

B A

N/A I

N/A B

A 1E 6.

Pump motors 7.

Valves, isolation LPCI

- ):

m >-

line 1

I A

-B (g)

D,A,C 1R.

.. l. $T S.

Valves, isolation other 2

I B

B.

(g)

D,C,A 1E '

-8g 9.

Pump. suction from

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suppression pool, piping, o!

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valves, including

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m 5 -

2; I

B B

(g).

A 1E

-u isolation valves o-

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2 3.2-15 g;..

v.

c

il CPS-USAR Revision 6 May 1995 TABLE 3.2-1 (Cont'd)

QUALITY QUALITY 6 GROUP ASSURANCE SAFETY SEISMIC CLASSI-REQUIRE-ELECTRICAL PRINCIPAL COMPONENTSfsI CLASSfb)

CATEGORYfc)

FICATIONfdi MENTSfel COMMENTS LOCATIONfsi CLASSIFICATIONft1

2) Piping, Valves, Compressors upstream of Air Receiver Tank Inlet Check Valve, downstream of Air Receiver Tank drain valve Other N/A D

N/A S

non-lE

3) Compressors other I**

D N/A S

non-1E

- Non-safety compressors seismically cupported b) Engine Skid 3

I D

B (11)

S N/A 8.

Diesel generators 2

I N/A B

S 1E 9.

a) Diesel generator exhaust silencer and screen grating Other I

D N/A N/A b) Diesel generator exhaust piping 3

I D

B (kk)

S N/A c) Exhaust piping i

on diesel engine 3

I D

B (11)

S N/A

10. Electrical modules with safety. function I

N/A B

(w)

N/A 1E

11. Cables with safety

]

function I

N/A B

N/A 1E

12. Diesel engine cooling m>'

jacket water system 3

I C

B (11)

S 1E g"

13. Diesel engine lubrication system 3

I D

B S

1E u S. -

ea

14. Combustion air system og to filter inlet 3

I C

B S

N/A mu

15. Air dryers and associated piping, u"*

controls, and cables Other I

D N/A S

N/A g

c S.

3.2-27 e

g

.+

a.;

7

' Attachment 5'

j to U-602469 -

.Page1ofI This attachment responds to the NRC reviewer's comments regarding certain amendments previously made to the CPS USAR.~

'{

(1)

Section 1.8 of the USAR, which contains the CPS position on confonnance l

to RG 1.33, takes exception to the provision in ANSI N18.7-1976 for biennial reviews of procedures. The NRC reviewer commented that the'.

CPS position for plant procedure review was not consistent with guidance -

provided to the NRC staff and was unacceptable. IP understands that the j

NRC has internal guidance on this subject; therefore, to resolve this issue, j

IP willincorporate the NRC guidance into the CPS position. See.

,i of this letter for the proposed USAR page 1.8-48a..

j

!j (2)

US AR Table 3.2-1, " Classification of Systems, Components, and

'j Stmetures," item X.7, "RHR System, Valves, isolation LPCI line,". (page..

3.2-15) did not appear to the reviewer to have a seismic category. The :

seismic category for this item is present, but not on the same line as otherL l

information for this item. The seismic category has been realigned to be i

consistent with the other information provided for this item.' See of this letter for changed USAR page 3.2-15.

-l (3)

USAR Table 3.2-1, items XXVIII.6.a.1, " Starting Air System (Div. I and i

II), Air Start Skid, Inlet check Valve to Air Receiver Tanks to the Diesel,"

and XXVIII.7.a.1, " Starting Air System (Div. III), Inlet Check Valve to :

i Air Receiver Tanks to the Diesel," (page 3.2-26) were changed from -

l Quality. Group Classification C to Quality Group Classification D. The change was made to correct a classification error. The classification C 1

indicates that the piping was designed using ASME III as a guide vice

.]

ANSI B31.1 as indicated by classification D. The diesel air start skid j

supplier used ANSI B31.1 in the design of that equipment, thus, j

classification D is correct. As requested by Mr. Maura, Attachment 6 contains the 10CFR50.59 safety evaluation for this change.

(4)

USAR Table 3.2-1, item XXVIII.9.b, (page 3.2-27) was split into two items, " Diesel generator exhaust piping," and XXVIII.9.c, " Exhaust piping on diesel engine." The item previously was Quality Assurance L

Requirements category B but was changed to category B for the "dieself generator exhaust piping" and category N/A for the " exhaust piping on diesel engine" when the item wes split into two separate line items. QA program requirements are applied to category B items while QA program 4 requirements are not applicable to category N/A items. IP inve'stigation of l this issue identified that the category N/A applied to the " exhaust piping on diesel engine" was in error. A condition report was initiated to document the error. The error has been corrected and Attachment 4 contains corrected USAR page 3.2-27.

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.1 L1 to U-602469 PageIof30

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This attachment contains the 10CFR50.59 safety evaluation for changing the Quality.

[

Group Classification category of diesel generator air start skid as identified in USAR table i

3,2-1, items XXVIII.6.a.1 and XXVIII.7.a.1.

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oM SAFETY EVALUATION FORM 1.1 IAS Log #91-00%

Document Evaluated:

1.2 Number

DGF037

1.3 Revision

1.4

Title:

Field Alteration 1.5

" References :

USAR Table 3.2-1 Ficure 9.5-4 K-Soec M-2884 USAR Table 3.2-3 CR 1-89-11-003 9.5.6 USAR Table 9.5-2 REG Goit>tr f.d C, Yn 1&s 91 USAR Table 9.5-10 FECN 24920 BIDCK A - DESCRIPTION OF CHANCE (Use additional pages if required)

A.1 Describe the basic document or system and the changes being made:

The emergency diesel generators (EDCs) are required to supply the Class 1E, 4.16 KV buses during emergency conditions. Therefore, the diesel generators are safety related.

Condition Report 1-89-11-003 was initiated to identify that 4 flexonics hoses were purchased as Level IV, non safety and not safety class 3 as they should have been. Upon investigation of this condition report severalinconsistenteswereidentifiedbetweenthepipeclasses*andthf.g i

g USAR safety classesTfor the EDCs which caused confusion,during psn.

purchasing. 4 CW * *** P'P!"G * *O '* *TML C S A" * *1M G

1L PtPsNG LisYs W 4 cxown ta UCAst ~racur 3.2-l Go p By revising the quality group, safety and pipe classifications and correcting the USAR Table 3.2-1 the confusion will be eliminated.

Currently, the USAR Table 3.2-1 has the diesel generator classified as

'~

safety class 'Other'.

This is incorrect for equipment which provides or supports any safety system function. 'Iherefore, they were changed to safety class 3, which supports the definition in the USAR 3.2.3.3.

Also some items are classed as Quality Croup C.

This classification only applies to items constructed to the ASME Code. The diesel contains numerous items which are not constructed to this code but which are safety-related. Therefore, per Reg. Cuide 1.26, if an item is safety-related but not constructed to ASME Code, it must be Quality Croup D.

The starting air system components have been classified Quality Croup D as a minimum.

Continued on Page 6.

A.2 Identify the equipment,' systems and parameters that may be affected by the change:

Diesel Generator System USAR Table 3.2-1 Valve and Equipment Lists NP-002-1 (10/89)

M1994/H91

Attechment 6 to U-602469' m

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1' 1

7 i; BIDCK B -- RADWASTE TREATMENT SYSTEMS

.8.1 The' proposed activity involves a modification'to a -

Yes j

radiological waste treatment system.or the way in which' it is operated as described in Chapter 11 of the SAR.

No X

l B.2 Because:

No. because the diesel renerator system is not nart of the Radwaste System as described in Chacter 11 of the CPS USAR.

..]

. If B.1 is yes, complete form NF-003.

4 BIDCK C - TECHNICAL SPECIFICATION IMPACT t

C.1 The proposed activity requires a change to any part of the Yes Technical Specifications.

No X'

C.2 Justification if "NO", Technical Specification change package identification number if "YES".

No. because Tech. Snee. does not address the safety class or nine class of the diesel.

l s

e BIDCK D - UNREVIEVED SAFETY QUESTION DETERMINATION (Attach additional pages with the responses to the block D questions.

Identify your answers to Parts I, II, III, and IV.)

Part I - Impact on equipment malfunctions evaluated as the design basis 1.

For the equipment and systems identified in A.1 and A.2, identify any l

' failures evaluated in the SAR.

2.

Discuss the impact of the change on the performance of the equipment and -

systems identified in A.1 and A.2.

3.

Identify what new failure modes could be introduced by the change.

l 4.

Identify any impact of the change on the consequences of.the failures j

evaluated in the SAR.

}

l S.

Identify any. impact of the change on the probabilities of the failures evaluated in the SAR.

j NF-002-2 (10/89)

M1994/M91,

. ~..

Attachmsnt 6'to U-602469 c, _

l

.23 9

Pags 4 of 30

%oN6 4

i SAFETY EVAIEATION FORM BIDCK D - UNREVIEWED SAFETY QUESTION DETERMINATION

SUMMARY

Based on item 4, are the consequences of any malfunction YES

f equipment evaluated in the SAR increased?

NO X

o Based on item 5, is the probability of a malfunction YES of equipment evaluated in the SAR increased?

NO X

l If the answer to any of the above questions is yes, the change is an unreviewed safety question.

Part II - Impact on the accidents evaluated as the design basis 1.

Identify.the accidents evaluated in the SAR which could be affected by the change.

2.

Discuss how the change impacts the consequences of these accidents.

3.

Discuss how the change impacts the probability of these accidents.

SUMMARY

Based on item 2, are the consequences of an accident '

YES evaluated in the SAR increased?

NO X

l Based on item 3, is the probability of an accident YES evaluated in the SAR increased?

NO X

-l If any of the above questions is answered yes, the change is an

?

unreviewed safety question.

Part III - Potential for Creation of a New Unanalyzed Event 1.

Based _ on Part I, items 1 and 3, could this change initiate a new type of j

accident or equipment malfunction? Discuss the basis for this determination.

2.

Determine if the new accident or malfunction identified above' has sufficient probability or consequences to be considered in the Licensing basis. Discuss the bases for this determination.

]

i NF-002-3 (10/89)

Eems

Attechment 6 to U-602469 y3 Page 5 of 30-l-40$b '

r u

SAFETY EVALUATION FDRM BIDCK D - UNREVIEWED SAFETY QUESTION DETERMINATI' N I

O L

SUMMARY

)

" Based on item 2, does the change create the possibility.

YES l'

for an equipment malfunction or accident not evaluated NO X

in the SAR7 If the answer if yes, the change represents an unreviewed safety question.

Part IV - Impact on the Margin of Safety 1.

Identify how any of the protective barriers are directly affected by the change.

~

2.

Discuss the impact of the change on the approach to the acceptance limits for any of the protective barriers.

3.

Discuss the impact of the change on the bases of the Technical Specifications.

SUMMARY

Based on item 2, is any parameter in chapter 7 of the YES Safety Evaluation Manual exceeded?

NO X

Based on items 2 and 3, does the change reduce the margin YES of safety provided for the protective barriers?

NO X

If the first of these two questions is answered yes, the change may be unsafe and requires further justification.

If the first question is answered no and the second is answered yes, the change is safe-to implement but is an unreviewed safety question'and requires prior NRC approval.

NP-002-4 (10/89) anow em___________

Attachatnt 6 to U-602469 V'..**-

Page.6 of'30 Wh

,.s,

g' SAFETY EVAIEATION FORM BIDCK E -

SUMMARY

Based on the evaluation in Block C and Block D, the change

_.K._ is safe and is not an unreviewed safety question and requires no j

Technical Specification change.

j

-is safe but is an unreviewed safety question or requires a Technical Specification change.

is unsafe and cannot be ' implemented.

{

sd Preparer.

% C4/2/

A-M g-Jto 9/ '

' printed name

/

signatur A

s$te

[

Department Head IoHM

@SM

?

printed name Wtu&

date

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-[

Manager, NSED N

printed name A

signature date 491

b-U$44 kd'/

Manager, IAS printed name

&ignature date fk &f0l hl$~0 pga V

. printed dame signature date EVIDENCE OF NRC APPROVAL, IF REQUIRED:

'i i

-l i

N /A W 8-9-91 i

printed name

signature date l

The department responsible for vaulting the parent document must vault this completed form with the document evaluated.

o I

1

)

NF-002-5 (10/89) j

!M1994/M91:

Attachm2nt.6 to U-602469<

'3' Paga 7 of 30

$/g[

y

_3

's Block A

. Description of Change (Continued) 3 Irv.\\ ah -h D

Thechangesinpipeclasseshntheinst ent,' pipe and valve. data sheets A.1 require corresponding changes to USAR Table 3.2-1 for safety pV classification of equipment.. It is judged that the piping classe,s$r%e g-commensurate with the function it performs relating to the EDGs. To support the piping changes, a paragraph will be added to Spec. K-2884,

. stating that diesel generator component supports shall be maintained to -

meet ASME Section III, Subsection NF, Class 3.

Also included in this field alt. are changes to document as-built conditions such as:

(These' changes do not require revision of the USAR, and do not require a safety evaluation.)

p 1)

The as-built condition of IDGOSMB, flexible exhaust connection has a 22 inch inlet and outlet.

L l

2)

Equipment list D2-5945 Sheet i needs to be revised to delete 1DG02ME and MF because GE is the supplier, not Pathway Bellows.

j 3)

The valve list and ME-01.00 needs to show 1DG172 and 1DC173 as 1 1/2" valves.

4)

Valve, item 11 on 945E621 sheet 8, needs to be revised to show the valve as 1".

5)

Flex hose, item 21 on 945E621 sheet 8, needs the description changed I

. 3,,,

by deleting "with 2 NPT nipples" and including new part number l

DJ214A9606 which is a new administrative part number change.

8 I

Block D Part I l

l 1)

CPS USAR Table 9.5-2 evaluates a loss of the fuel oil system taa diesel generator. The fuel oil failures identified are loss of one storage l

tank, loss of one day tank, loss of one transfer pump and a line rupture.

CPS USAR Table 9.5-10 describes and evaluates the loss of the, air starting system components. The air starting system failures identified-are the loss of one compressor, loss of one receiver tank,- loss of one subsystem, pipe ruptures, and loss of an entire starting air system.

The loss of one diesel generator and its associated load will not prevent.

safe shutdown of the plant / reactor since each diesel generator is l_

divisionally separate.

2)

Performance of the diesel generator and associated subsystems are not impacted by the change because no physical changes are being made. The technical requirements of the specific component remain unchanged (i.e.,

300'psig hedule 40 pipe). This change revised the classification of the pipin from ASME Class 2 to ANSI B31.1 with a certificate of 3

Conformanc. Manufacturing methods and materials would be equivalent.

ASME does provide more documentation (i.e., traceability to specific heat' numbers of base materials). Although this provides greater traceability, NF-002-6 (10/89)

If La.am6 Rest. Jfo>cs,

@J d/ '

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L

..M1994/M91 W*

I4. 50 d e'

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Attachment'6'to U-602469 Page 8 of 30 it does' not assure a product of higher quality than ANSI B31.1 with a Certificate of Conformance. In addition, ANSI B31.1 piping is equivalent to other DG air start piping. 'As such, this change will provide the same level of performance for the systems identified in A.1 and A.2.

3)

No new failure modes can be introduced by the change than already identified.

4)

The consequences of the failures identified in D.I.1 have not been changed, because no physical changes have been made.

(See Block D.I.2) 4 5)

The probability of failure.of EDG systems has not increased by the change in design / quality requirements because the change is judged to be a-insignificant compared to the expected / required reliability of the EDGs.

(See Block D.I.4) e Part II f

1.

The accidents identified in the USAR will not be affected by the' change because the change in the design / quality is judged to be insignificant in j

affecting the accidents identified in the USAR.

2.

See Part 11.1.

'3.

See Part 11.1.

t Y'

Part III l

l 1.

This change will not initiate a new type of accident, because the change in the documented design / quality is judged to be insignificant.

2.

See Part III.l.

l Part IV 1.

None of the protective barriers or margins of safety are directly affected by this change, the technical requirements of the specific l'

component remain unchanged. The documentation of the component is changed and the difference is negligible.

t 2.

See Part IV.I.

3.

This change does not impact the Tech. Spec. bases.

(See Part IV.1.)

1 I

1 i

a 1

NF 002-7 (10/89) j M1994/M91 1

Attachmsnt 6 to U-602469 Paga 9 of 30 i

FIELD ENGINEERING CHANGE NOTICE 1

JIO-CPS-

~~

NO.24920 PAGE __1_ OF 20 1.

2.

3. DESIM CNIHL REVIEN EIN VARIOUS-SYS. DG Q REUMD

[N]

Q [N]

4.

FIO IEE 5.

[ ] HER [ ] G DISP.

[x] DESIGN GANGE NmmIZATICH 10.

6.

AITwiw DOOMENIS FOSF INO]REGATION 1%2u11c2; x

D2-5945 Sheet 1 x

DG Pisim, Valve, Sneciality, (nlitzent lists

>(

K-2884 7.

IrX2urriCN OF GANGE/ ACTIN 1.

Revise affected rh'=orits as detailed on pages 2 thrugh 20 to correct the t'la"ification of the diesel " r-aiw to pip 2 class 'o' do%uuais of the air

^

receiver inlet check valve and pipe class 'D' tif=Leme of the same valve. Add paragraph to Spec. K-2884 similar to 301.10 for the Diesel Generator System (D3)

<xxuponent suppis, in order to retain the nuclear safety-related cinmification.

'Ibe equipnent so designated on the diesel generators do perform a safety function and will be covered by a 10CER50 Appendix B swa.mu.

2.

Revise 1DG08MB size to 22 inches inlet and outlet (pg 12).

3.

Delete 1DG02ME and 1DG02MF from list of equipnent on D2-5945 sheet 1.

See G 1-89-11-003.

8.

JUSI'IFICATICN 1.

Previous r lamifications of the above affected equipnent have 1 to' confusion as to how rap 1ww==nt parts and/or whole umpuis should be purchased. 'Ibe revised t'lamification and correction of the' TEAR will eliminate this potential confusion. 'Jhe ax;t limiting of the DG components affected already had this r-lamification which est ahlmhes the miniinum requirements for all the affected equipment. 'Ihis change makes the classification of the DG equipnent uniform.

2. 'Ihis is rm-wy to rh'=prit the as-built condition.

3.

Subject flexhoses were not made by Pathway Bellows but by GE. It is therefore mory to remove them from the Pathway drawing.

//b T_, IRINF NAME R,C. Kefauver DISCIlkb8 NSED-MEG PREPARER

10. REVIEMERS

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DISCIPGNE DISCIPLINE

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._..____._;~_....__ _ _ _ _ _ _ _ _, _ _
- to U-602469
..o Page 29 of 30 A.
y /' ifc-ces E. LEE.D ENGINEERING C,HANGE 'NOTtCE NO.24924 p.,
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4: OtsiGN cnNTRote nEviEw j
c-EIN Various
. SYS. DG' Q REf.ATEO (Y) (N]
((j p {p}
4.FECH USE
5. AUTHontuTION HO.
~
[ ]MER
(]CR OBSH
()l DESIGN CHANGE POST INCORPORATIO N G. AFFECTED DOCUMENTS REQUIRED 945E621. sheet 8 1
" ~ -
0 F
?
DG 'vhlve-list x
/////P/
K7R61-nn69n MNY/78/ '
K2801-0076C x
Eng. Stand'ard ME-01.00 Sf1 DG-02 Y
~
7. DESCRIPTION OF CHANGE / ACTION 1.
Revise the valve list and ME-01.00 to show 1DG172 and 1DG.173 as lh" valves (PRFI 9301) 2.
Revise item 11 on 945E621 sheet 8 description to show that valve l
is 1" in size.
I 3.
Revise item 21 on 945E621 sheet 8 desci-iption deleting "Vith 2" NPT nipples" and add new GE part number DJ214A9606.
ia I
l
)
a JUSTIFICATION 1.
VPF 5244-006 and walkdown confirms that these valves are lh"
. This change is necessary to make the design documents consistant.
2.
M05-1035 valve list and walkdown confirm.that this valve is 1" in size.
The change is required to make the design documents consistant.
3.
Walkdown and GE documentation confirm'these flex hoses have weld '
neck flanges not NPT connections.
The"new part number is a internal GE. Change to des,ignate the flexhoses as safety related.
This is riot a designwhange but an administrative part number
~
change.
[/ /!/[ PRINT NAME R.C. Kefauver otSCIPLINENSED PREPARER IO. REVIEWERS E
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OISCIPLI NE OlSCIPLINE
/
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OtSCIPLINE
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ate D
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A HAV M M M M M M M M M M
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f CPL EEA NO MDV I
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6 8 7 7
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9 0 1
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7 7
7 7
7 7 7
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7 7
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7-7 7
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V U G
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R R
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A A
A A A A A 3
E
_

ML20086U283

Contents

Text

8.2 DESCRIPTION

18.2 DESCRIPTION

Reference:

1.2 Number

1.3 Revision

Title:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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ML20086U283

Text

8.2 DESCRIPTION

18.2 DESCRIPTION

Reference:

1.2 Number

1.3 Revision

Title:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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