Text

To ASME Code Section XI Inservice Insp & Testing Program & Info Required for NRC Review of Requests for Refief from ASME Code Section XI Requirements
	ML20039E083
Person / Time
Site:	Prairie Island
Issue date:	12/23/1981
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20039E076	List: ML20039E075; ML20039E083;
References
	NUDOCS 8201060510
	Download: ML20039E083 (9)
	v • d • e

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23,-1981-D:ic:.mbar

Revision No. 7 to Prairie Island ASME' Code Section XILInservice Inspection s

and Testing' Program and Information Required for NRC Review of Requests -

for Relief-from ASME Code Section XI Requirements, dated February 1, 1978 Remove the Following

- Insert the Following Pages Revision No.'7 Pages Title'Page-

. Title Page.

'l iii & iv

' iii & iv i

- 1.4--11 1.4 !

1.5-77 (new page) 2.4-11

- 2.4-11

- 2.5-60 (new page) l l

I Use the " Record of Revisions," pages iii and iv to verify your copy of the.

program manual' is complete and up-to-date following ' entry of this revision.

8201060510 811223 PDR ADOCK 05000282 O

PDR

NORTHERN STATES. POWER COMPANY PRAIRIE. ISLAND NUCLEAR GENERATING PLANT.

DOCKET NOS. 50-282' LICENSE NOS. DPR-42 50-306 DPR-60 ASME CODE SECTION-XI INSERVICE INSPECTION AND' TESTING PROGRAM AND

. INFORMATION REQUIRED FOR NRC REVIEW OF REQUESTS FOR RELIEF FROM.

ASME CODE SECTION XI-REQUIREMENTS:

-SUBMITTED:

F'ebruary 1, 1978 REVISED: Revision 1 September 15, 1978-Revision 2 June 8, 1979 Revisi in 3 Septe oer~ 19, 1979 Revision 4 April 17, 1980 Revision 5-September 3, 1980 Revision 6-July 31, 1981 Revision 7

December 23,:1981

RECORD OF REVISIONS Page No Revision No Page No Revision No Cover 7

1.5-1 2

ii 4

1.5-2 thru 1.5-5 1

iii 7

1.5-6 Original iv 7

1.5-7 1

1-1 4

1.5-7A 1

1.1.1-1 4

1.5-7B 2

1.1.1-2 thru 1.1.1-4 6

1.5-10 1

1.1.1-5 thru 1.1.1-6 Original 1.5-11 Original 1.1.1-7 1

1.5-12 1

1.1.1-8 thru 1.1.1-10 Original 1.5-12A 2

1.1.1-11 6

1.5-13 Original 1.1.1-12 thru 1.1.1-17 Original 1.5-14 Original 1.1.1-18 1

1.5-15 1

1.1.1-19 Original 1.5-15A 1

1.1.1-20 1

1.5-16 1

1.1.1-21 thru 1.1.1-25 Original 1.5-17 Original 1.1.1-26 thru 1.1.1-28 6

1.5-18 1

1.1.1-29 thru 1.1.1-33 Original 1.5-18A 1

1.1.1-34 6

1.5-19 Original 1.1.1-35 Original 1.5-20 1

1.1.1-36 6

1.5-22 thru 1.5-23 Original 1.1.1-37 thru 1.1.1-39 Original 1.5-24 2

1.1.;-1 4

1.5-25 6

1.1.2-2 thru 1.1.2-27 6

1.5-27 thru 1.5-28 Original 1.1.3-1 4

1.5-29 1

1.2-1 6

1.5-30 Original 1.3-1 4

1.5-31 thru 1.5-34 1

1.3-2 1

1.5-34A 1

1.4-1 4

1.5-35 Original 1.4-2 1

1.5-36 6'

1.4-3 thru 1.4-4 2

1.5-37 thru 1.5-39 Original 1,4-5 4

1.5-40 1

1.4-6 1

1.5-41 Original 1.4-7 thru 1.4-8 4

1.5-42 1

1.4-9 2

1.5-43 2

1.4-10 1

1.5-47 Original 1.4-11 7

1.5-48 6

1.4-12 2

1.5-50 1

1.4-14 thru 1.4-15 2

1.5-51 Original 1.4-16 1

1.5-52 thru 1.5-55 6

1.4-17 6

1.5-56 3

1.4-18 4

1.5-57 thru 1.5-58 Original 1.4-19 thru 1.4-20 1

1.5-59 6

1.4-21 4

1.5-60 1

1.4-22 1

1.5-61 thru 1.5-62 Original 1.4-23 4

1.5-63 6

1.4-24 thru 1.4-34 1

1.5-64 thru 1.5-68 1

1.5-69 2

1.5-70 4

1.5-71 thru 1.5-72 1

1.5-73 2

1.5-74 4

1.5-75 thru 1.5-76 6

1.5-77 7

2.1 4

2.1.1-1 4

iii 2.1.1-2 6

Revision 7 12/23/81

]

RECORD OF REVISIONS Page No Revision No Page No Revision No 2.1.1-3 6

2.5-10 thru 2.5-11 2

2.1.1-4.

1 2.5-11A 2

2.1.1 6 2.5-12 1-2.1.1-6 thru 2~.1.1-7 Original 2.5-13 Original 2.1.1-8 thru.2.1'.1-9 6

2.5-14' 1

2.1.1-10 Original 2.5-15 thru 2.4-20 Original

2.1.1-11 6

2.5-21 6

2.1.1-12 thru 2.1.1-13 Original 2.5-23 thru 2.5-24 Original 2.1.1 6 2.5-25 1~

2.1.1-16 thru 2.1.1-18 Original

'2.5-26 1

.2.1.1-19 6

2.5-26A 1

2.1.1-20 thru 2.1.1-25 Original.

2.5-27 Original 2.1.1-26 1

2.5-28' 6

2.1.1-27.thru 2.1.1-30 Original

.2.5-29 1

-2.1.1-31 6

2.5-30 1

2.1.1-32 thru 2.1.1-33 Original 2.5-31 2

2.1.1-34 thru 9. 1.1-35 6 2.5-33

'6

-2.1.1-38^

3 2.5-34 1

~2.1.1-39 thru 2.1.1-41 Original 2.5-35 1

2.1.2-1 4

2.5-36 Original 2.1.2-2 thru 2.1.2-24 6

2.5-37.thru-2.5-40 6

2.1.3-1 4

2.5-41.thru 2.5-43 Original.

-2.2-1 6

2.5-44 6

2.3.1 4

2.5-45 1

2.3.2 Original 2.5-46 thru 2.5-47

. Original 2.4-1 4

2.5-48.

-6 2.~4-2 thru 2.4-4 2

.2.5-49 thru 2.5-53 1 ~

2.4-5 4

2.5-54 4-2,4-6 thru 2.4-7 1

2.5-55 thru 2.5-56 1

2.4-8.thru 2.4-9 4

2.5-57 4

2,4-10 2

2.5-58 thru-2.5-59 6

2.4-11 7.

2.5-60 7

2.4-12 thru 2.4-13 1

3-1 thru 3-8 6

2.4-14 6

4-1 2

2.4-15; 4

4-2 thru 4 Original 2.4-16 1

4-5 thru 4-6 2

2.4-17 6

4-7 thru 4-9 Original 2.4-18 thru 2.4-28 1

4-10 thru 4 -2' 2.5-1 2

4-14 thru 4-19 Original 2.5-2'thru 2.5-4 1

4-20 thru 4-22 2-2.5-5 Original 4-23 Original 2.5-6 1

4-24.

2 2.5-6A 2

4-25 thru 4-31 Original 2.5-8'thru 2.5-9 Original 4-32 2

4-33 thru 4-39 Original 4-40 2

-iv--

Revision 7 12/23/81

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b; ASME CODE VALVES-SYS FLOW DIAGRAM VALVE NO.

CLASS DWG DESCRIPTION VLV CAT TEST PROC P

FRE R IF RCP SEAL WA7JJR FILTER CVC X-HIAW-1-38 VC-25-1 4

LINE RELIEF C

SP-1154'(1)

SP SY CVC X-HIAW-1-38 VC-26-1 4

LETDOWN LINE RELIEF

'C SP-1154(1)

SP'

'SY

~

CVC X-HIAW-1-38 VC-8-7 4

11 RCP SEAL LINE CHECK-C SP-1166 E

R

39 CVC X-HIAW-1-38 VC-8-6 4-12 RCP' SEAL LINE CHECK C

SP-1166 E

R

39 CHARGE LN CHECK DWNSTRM r

CVC X-HIAW-1-38 VC-8-2 4

REGEN HX C

27 1 REAC CLNT LOOP PZR

, CVC X-HIAW-1-7 CV-31226 2

LTDN LN ISOL B

SP-1162 E'

R

35, #18 y

1 REAC CLNT LOOP'PZR-p CVC X-HIAW-1-7 CV-31255 2

LTDN LN ISOL B

SP-1162 E

R

35, #18 CHARGE LN CV-31328 l

CVC X-HIAW-1-38 VC-17-1 4

BYPASS CHECK C

27 k

n;1 C

58

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4

65

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-5' VCT' RELIEF

'C SP-1154(1)~

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65. REQUEST FOR PELIEF ASME COMPONENT FUNCTION Code V1v Class Cat VC-24-1 VCT Relief Protect Volume Control Tank fram system 2 -

C overpressure CODE REQUIREMENT The relief valve setpoint will not be verified at the frequency required by IWV-3510(a).

BASIS Extensive operational problems are created in.trying to verify the setpoint of these valves. Removing the valves from service requires shifting waste gas inventories to allow isolation of the valve generation of additional waste gas required for purging of associated equipment 'to climinate 112 explosion problems and to minimize radiation levels, and gas releases required to affect purge of the equipment to' allow maintenance operations.

Testing _the valves in place is not practical considering the possibility of overpressurizing associated tanks or equipment or having.the valve stick open and causing an uncontrolled release of radioactive material.

[

ALTERNATE INSPECTION (TESTING)

I j

These valves will be tested whenever maintenance-develops that requires the associated equipment to be removed from service.

SCHEDULE FOR IMPLEMENTATION When required.

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65. REQUEST FOR RELIEF ASME COMPONENT FUNCTION Code-Viv Classi

' Cat 2VC-24-1 VCT Relief-Protect Volume Control Tank fram system 2-C

-overpressure CODE REQUIREMENT The relief valve setpoint will not be verified at the frequency required by IWV-3510(a).

BASIS Extensive operational problems are created in trying to verify the setpoint of these valves. Removing the valves from service requires shifting waste gas inventories to allow isolation of the valve, generation of 2 exP osion problems and to l

additional. waste gas required for purging of associated equipment to climinate H minimize radiation levels, and gas releases required to affect purge of the equipment to allow maintenance operations.

Testing the valves in place is not practical considering the possibility of overpressurizing associated N

-sp tanks cn: equipment or having the valve stick open and causing an uncontrolled release of-radioactive material.

-ALTERNATE INSPECTION (TESTING)

These valves will be tested whenever maintenance. develops that requires the associated equipment to be removed from service.

SCHEDULE FOR IMPLEMENTATION When required.

4 m

$2.&

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To: Dircctor cf Nuciscr Roccter Rigulation Date:

Dec==her 23. 1981 U S Nucicer Rigulatcry Commissien Washington, DC 20555 Licensing Fee Determination Fee Type: Facility License Amendment Reqbtred Approval y

Materials License Application Materials License Renewal Other (Description

)

Licensee: Northern States Power Company _,

Plant:

Prairie Island Nuclear Generating Plant Docket No. 50- 282

' license No. DPR-42 Materials License No.

50- 306 OPR-- 60.

t Date and subject of Licensing Request:

Information Required for NRC Review of Inservice Inspection and Testing Program-and Requests for Relief from ASME Code R.cei nn YT Requir -.nen ame.A n.c -hor 91_14R1-License Amendment or Approval Class:

III

. Fee:

$4000.00 Class:

I Fee:

$ 400.00 Materials License Category:

Fee:

Total Fee Enclosed:

$4400.00 Basis for determination of fee class:

This is a revision of the Prairie Island Nuclear Generating Plant ASME' Code Section XI Inservice Inspection and Testing Program.

It-is being submitted in accordance with 10 CFR Part 50, Section 50.55a(g)(5). Commission review of Code requirements we have-found to be impractical is required.

This is a required approval involving a. single safety issue. Standards of acceptability have been clearly identified by NRC Staff positions.

l 1

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is Prepared by: Nuclear Support Services Department t

Northern States Power Company 4

414 Nicollet Mall - 8th Floor 5 -

Minneapolis, MN 55401 (612) 330-6763

~.

cc NSS File

_

ML20039E083

Text

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