ML19305E366

to ASME Code XI Inservice Insp & Testing Program & Info Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements.

ML19305E366
Person / Time
Site:	Prairie Island
Issue date:	04/17/1980
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML19305E364	List: ML19305E363 ML19305E366
References
PROC-800417, NUDOCS 8004230487
Download: ML19305E366 (35)

Text

_ _

s e O April 17, 1980 Revision No. 4 to Prairie Island ASME Code Cection XI Inservice Inspection 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. 4 Pages Title Page Title Page ii ii iii iii iv iv 1-1 1-1 1.1.1-1 1.1.1-1 1.1.2-1 1.1.2-1 1.1.3-1 1.1.3-1 1.2-1 1.2-1 1.3-1 1.3-1 1.4-1 1.4-1

= 1.4-5 1.4-5 1.4-7 1.4-7 1.4-8 1.4-8 1.4-18 1.4-18 1.4-21 1.4-21 1.4-23 1.4-23 1.5-70 1.5-70 1.5-74 1. 5- 7.4

(h 2-1 2.1.1-1 2-1

\- / 2.1.1-1 2.1.2-1 2.1.2-1 2.1.3-1 2.1.3-1 2.2-1 2.2-1 2.3-1 2.3-1 2.4-1 2.4-1 2.4-5 2.4-5 2.4-8 2.4-8 4

2.4-9 2.4-9

2.4-15 2.4-15 2.4-17 2.4-17 2.5-54 2.4-54 2.5-57 2.4-57 i 1

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. ,

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NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 LICENSE NOS DPR-42

! 50-306 DPR-60 I

! ASME CODE SECTION XI INSERV7CE INSPECTION AND TESTING PROGRAM

, AMD l INFORMATION REQUIRED FOR NRC REVIEW OF REQUESTS FOR RELIEF FROM I

ASME CODE SECTION XI REQUIREMENTS

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SUBMITTED: February 1,1978 REVISED: Revision 1 September 15, 1978 Revision 2 June 8, 1979 Revision 3 September 19, 1979

, Revision 4

'O April 17, 1980 s

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TABLE OF CONTENTS SECTION PACE Record of Revisions lii 1 Unit No. 1 and Common Components 1-1 1.1 Nondestructive Examination Program 1.1.1-1 1.1.1 Class 1 1.1.1-1 1.1.2 Class 2 1.1.2-1 1.1.3 Class 3 1.1.3-1 1.2 Pressure Testing Program 1.2-1 1.3 Inservice Testing of Pumps 1.3-1 1.4 Inservice Testing of Valves 1.4-1 1.5 Requests for Relief from ASME Code Section XI 1.5-1 Requirements Determined to be Impractical 2 Unit No. 2 Components 2-1 2.1 Nondestructive Examination Program 0 2.1.1 Class 1 2.1.1-1 2.1.1-1 2.1.2 Class 2 2.1.2-1 2.1.3 Class 3 2.1.3-1 s 2.2 Pressure Testing Program 2.2-l' 2.3 Inservice Testing of Pumps 2.3-1 2.4 Inservice Testing of Valves 2.4-1 2.5 Requests for Relief from ASME Code Section XI 2.5-1 Requirements Determined to be Impractical 3 Prcposed Technical Specification Changes 3-1 4

ASME Code Classification - Units No. I and 2 , 4-1 1

l

' O 'il Revision 4 4/17/80

' k' i

RECORD OF REVISIONS

(' Page No Revision No Page No Revision No Cover 4 1.5-1 2 ii 4 1.5-2 chru 1.5-5 1 iii 4 1.5-6 Original iv 4 1.5-7 1 1-1 4 1.5-7A 1 1.1.1-1 4 1.5-7B 2 1.1.1-2 Original 1.5-10 1 1.1.1-3 1 1.5-11 Original 1.1.1-4 thru 1.1.1-6 Original 1.5-12 1 1.1.1-7 1 1.5-12 A 2 1.1.1-8 thru 1.1.1-17 Original 1.5-13 Original 1.1.1-18 1 1.5 14 0,riginal 1.1.1-19 Original 1.5-15 1 1.1.1-20 1 1.5-15A i 1.1.1-21 thru 1.1.1-26 Original 1.5-16 1 1.1.1-27 3 1.5-17 Original 1.1.1-28 thru 1.1.1-33 Original 1.5-18 1 1.1.1-34 1 1. 5-18 A 1 1.1.1-35 Original 1.5-19 Original 1.1.1-36 3 1.5-20 1 1.1.1-37 thru 1.1.1-39 Original 1.5-22 thru 1.5-23 Original 1.1.2-1 4 1.5-24 2 1.1.2-2 thru 1.1.2-3 Original 1.5-25 thru 1.5-28 Original 1.1.2-4 thru 1.1.2-5 3 1.5.-29 1 1.1.2-6 thru 1.1.2-9 Original 1.5-30 Original O's 1.1.2-10 3 1.5-31 thru 1.5-34 1 1.1.2-11 Original 1.5-34A 1 1.1.2-12 3 1.5-35 thru 1.5-39 Original 1.1.2-13 Original 1.5-40 1 1.1.2-14 thru 1.1.2-16 3 1.5-41 Original  !

1.1.2-17 thru 1.1.2-18 Original 1.5-42 1 1.1.2-19 thru 1.1.2-20 1 1.5-43 2 1.1.3-1 4 1.5-47 thru 1.5-48 Origitsi 1.2-1 4 1.5-49 1 1.3-1 4 1.5-50 1 1.3-2 1 1.5-51 thru 1.5-54 Original 1.4-1 4 1.5-55 1 1.4-2 1 1.5-56 3 1.4-3 thru 1.4-4 2 1.5-57 thru 1.5-59 Original 1.4-5 4 1.5-60 1 1.4-6 1 1.5-61 thru 1.5-63 Original 1,4-7 thru 1.4-8 4 1.5-64 thru 1.5-68 1 1.4-9 2 1.5-69 2 1.4-10 1 1.5-70 4 1.4-11 thru 1.4-12 2 1.5-71 thru 1.5-72 1 1.4-14 thru 1.4-15 2 1.5-73 2 1.4-16 thru 1.4-17 1 1.5-74 4 1.4-18 4 2.1 4 1.4-19 thru 1.4-20 1 2.1.1-1 4 1.4-21 4 2.1.1-2 Original  !

N 1.4-22 l

l (d 1,4-23 1.4-24 thru 1.4-34 1

4 1

l l

l iii Revision 4 4/17/80 )

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RECORD OF REVISIONS Page No Revision No Page No Revision No 2.1.1-3 1 2.5-10 thru 2.5-11 2 2.1.1-4 1 2.5-11A 2 2.1.1-5 thru 2.1.1-14 Original 2.5-12 1 2.1.1-15 3 2.5-13 Original 2.1.1-16 thru 2.1.1-18 Original 2.5-14 1 2.1.1-19 1 2.5-15 thru 2.4-24 Original 2.1.1-2d thru 2.1.1-25 Original 2.5-25 1 2.1.1-26 1 2.5-26 1 2.1.1-27 thru 2.1.1-37 Original 2.5-26A 1 2.1.1-38 3 2.5-27 Original 2.1.1-39 thru 2.1.1-41 Original 2.5 Original 2.1.2-1 4 2.5-29 1 2.1.2-2 thru 2.1.2-3 1 2.5-30 1 2.1.2-4 2 2.5-31 2 2.1.2-4?. 2 2.5-33 Original

?.1.z-5 Original 2.5-34 1 2.1.2-6 2 2.5-35 1 2.1.2-6A 2 2.5-36 thru 2.5-39 Original ,

2.1.2-7 Original 2.5-40 1 2.1.2-8 1 2.5-41 thru 2.5-44 Original 2.1.2-9 Original 2.5-45 1 2.1.2-10 3 2.5-46 thru 2.5-48 Original 2.1.2-11 Original 2.5-49 thru 2.5-53 1 2.1.2-12 1 2.5-54 4 2.1.2-13 Original 2.5-55 thru 2.5-56 1 2.1.2-14 thru 2.1.2-15 3 2.5-57 4 2.1.2-16 Original 3-1 thru 3-6 2 2.1.2-17 1 3-7 thru 3-13 Original 2.1.2-18 thru 2.1.2-20 Original 3-14 2 1

2.1.3-1 4 3-15 thru 3-16 Original 2.2-1 4 4-1 2 2.3.1 4 4-2 thru 4-4 Original 2.3.2 Original 4-5 thru 4-6 2 2.4-1 4 4-7 thru 4-9 Original 2.4-2 thru 2,4-4 2 4-10 thru 4-13 2 2.4-5 4 4-14 thru 4-19 Original 2,4-6 thru 2.4-7 1 4-20 thru 4-22 2 2.4-8 thru 2,4-9 4 4-23 Original 2.4-10 thru 2.4-11 2 4-24 2 2.4-12 thru 2.4-14 1 4-25 thru 4-31 Original 2.4-15 4 4-32 2 2.4-16 1 4-33 thru 4-39 Original 2.4-17 4 4-40 2 2.4-18 thru 2.4-28 1 2.5-1 2 2.5-2 thru 2.5-4 1 2.5-5 Original 2.5-6 1 2.5-6A 2 2.5-8 thru 2.5-9 Original

-iv- Revision 4 4/17/80

SECTION 1 UNIT NO. 1 AND COMMON COMPONENTS 7-~g This section contains a description of our proposed program of inservice

() inspection and testieg of components in Unit No. 1 of the Prairie Island Nuclear Generating Plant and components in systems common to both Unit No.

I end Unit No. 2. This program conforms to the requirements of 10 CFR 50, Section 50.55a(g).

The information presented in this section follows the recommendations contained in a letter dated November 24, 1976 from Mr D L Ziemann, Chief, Operating Reactors Branch #2, Division of Operating Reactors, USNRC, and in a letter dated January 16, 1978 from Mr D K Davis, Acting Chief, Operating Reactors Branch #2. The program is updated as required by changes to Section 50.55a(g) published in the Federal Register on October 7,1979.

Inservice inspection and testing requirements are updated at 120 month intervals to conform to the latest edition and addenda of Section XI of the ASME Code referenced in paragraph (b) of 10 CFR 50, Section 50.55a. This manual will be updated each time changes are made to the inservice inspection and testing program. Deviations from Code requirements are also documented for NRC Staff review in this manual.

The program description is arranged in the following manner:

Nondestructive Examination Class 1 - Section 1.1.1

/"') Class 2 - Section 1.1.2 V

Class 3 - Section 1.1.3 Pressure Tests - Section 1.2 Inservice Tests of Pumps - Section 1.3 Inservice Tests of Valves - Section 1.4 Deviations from Section XI - Section 1.5 Requirements Proposed changes to the Technical Specifications which implement this program on Unit No. I and common components were submitted to the Commission on October 15, 1976. A summary of these proposed changes is contained in Section 3 of this report.

System drawings showing ASME Code classification boundaries are included in Section 4 of this report. These drawings are used to define pressure test boundaries and identify those Class 3 components subject to visual inspection as part of the nondestructive examination program.

1-1 Revision 4

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ASME Section XI Nondestructive Examination Program (Class 1) - Un't No.1 and Connon Comnonents ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: April 16, 1977 to December 16, 1983 NOTES:

1. The following tables identify the specific Class 1 components and parts to be examined. These tables can be directly correlated with Table IWB-2500 and Table IWB-2600 of Section XI and identify the examination method for each listed item. The inspections that were performed during the first forty (40) months of operation are included. The tables show the amount of items required to be examined for each period and the corresponding percentage that will have been p

completed by the end of that period.

p p 2. Repairs will be performed in accordance with the applicable requirements of the latest edition h and addenda of the ASME Code,Section XI. However, if rules for a particular repair are not specified in Section XI, the original design specification and Construction Code of the' component or system, or later editions of the Construction Code or ASME Code Section III, either in their entirety or portions thereof, may be used.

LEGEND:

Examination method:

V - visual U.T. -

ultrasonic

,, R.T. - radiography

h S - surface examination, either liquid penetrant or magnetic particle RG g Inspection Period

• ' ONE - December 16, 1973 to April 16 1977 TWO -

April 16, 1977 to August 16, 1980 THREE -

August 16, 1980 to December 16, 1983

(3 0 '

V U V ASME Section XI Nondestructive Examination Program (Class 2) - Unit No.1 and Common Co=ponents ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: April 16, 1977 to December 16, 1983 NOTES:

, 1. The following tables identify the specific Class 2 components and parts to be examined. These tables can be directly correlated with Table IWC-2520 and Table IWC-2600 of Section XI and identify the examination method for each listed item. The tables identify the number of items required to be examined over a forty (40) year service lifetime, and the amount required for a

' ten (10) year inspection interval. The inspections that were performed during the first forty (40) months of operation are included, along with the corresponding percentage that was completed.

The tables also show the amount of items required to be examined during each period, and the percentage that will have been completed by the end of that period.

g 2. The' scope of the inspection program for Class 2 components was based on the exemption criteria ja of IWC-1220.

? ~.

3 In accordance with the requirements of IWC-2411 the nondestructive examinations were selected H

so that the total examinations completed over forty (40) years will be 1007. of the required examinations of the system or portions of the systems with a single stream or be equivalent to having performed 100% of the required examinations in one of the streams of a multiple stream.

system. The selection of pressure retaining bolting for. valves was based on the type, manufacturer, and design of valve and not on the total number of certain size valve bonnet bolts per system.

4. Repairs will be performed in accordance with'the applicable requirements of the latest edition and addenda of the ASME Code,Section XI. However, if rules for a particular repair are not specified in Section XI, the original design specification and Construction Code of the component or system, or later editions of the Construction Code or ASME Code Section III, either in their ,

entirety or portions thereof, may be used.

LEGEND:

Examination method:

,, V -

visual

h U.T. - ultrasonic Rig R.T. - radiography

$ S- - surface examination, either liquid penetrant or magnetic particle L' ,, Inspection Period ONE. -

December 16, 1973 to Apri5 16, 1977 TWO - April 16, 1977 to August 16, 1980 THREE - August 16, 1980 to December 16, 1983. '

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ASME Section XI Nondestructive Examination Program (Class 3) - Unit No. 1 and Con: mon Comnonents ASME Code Edition and Addenda: 1974 Edition through and including Suamer 1975 Addenda Program Period: April 16, 1977 to December 16, 1983 NOTES:

- 1. The classification diagrams identify the systens that are required for examination in accordance with IWD-2000.

2. The scope of the inspection program for Class 3 components is based on the classification of the plant's inspection boundaries and exemptions as allowed for in IWD-2600 and IWD-5200. The inspection program is in accordance with IWD-2400 (Inspection Schedule).

3. . Visual examination will be conducted ~for evidence of component leakaYe,"s'tructural distress, or g

corrosion when the system is undergoing either a system inservice test, component functional test, or a system pressure test.

4. Supports and hangers for components will be visually examined to detect any loss of support capability or evidence of inadequate restraint.

. 5. Repairs will be perfonned in accordance with the applicable requirements of the latest edition and addenda of the ASME Code,Section XI. Ilow ver, if rules for a particular. repair are not specified in Section XI, the original design s, tcification and Construction Code of the component or system, or later edit'.ons of the Construction Code or ASME Code Section III, either in their '

entirety or portions thereof, may be used.

1. LEGEND:

Inspection Period ONE - December 16, 1973 to April 16, 1977

&h IWO - April 16, 1977 to August 16, 1980 Cs IHREE - August 16, 1980 to December 16, 1983 NO -

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ASME Section XI Pressure Testing Program - Unit No. I and Comon Components ASME Code Edition and Addenda: 1974 Edition through and including Sumer 1975 Addenda Program Period: April 16, 1977 to December 16, 1983 , .

The system Code Class boundaries are established on the attached ASME Code Classification Drawings, Sheets 2 through 40. The Pressure Test Program for the Class 1, 2, and 3 systems is as follo.is:

ASMF TEST TEST TEST SPECIFICATION REQUEST FOR RELIEF .

CODE CLASS TYPE FREQUENCY Leakage refueling IWB-5210(a) #20, #60 IWB-5221 IWA-5000 1

Hydrostatic 10 years IWB-5210(b) #20 l p IWB-5222 Io IWA-5000 A.

2 Pressate 10 years IWC-2412 #19, #20, #29 IWC-2510 3 Pressure 10 years IWD-2410(b) f20,#28,#30,

1. 31 3

= -

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a

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

ASME Section XI Pump Testing Pregram - Unit No. 1 and Cnnmon Component _s_

ASME Code Edition and Addenda: 1974 Edition through and including Sumer 1975 Addenda Program Period: April 16, 1977 through December 16, 1983 $

0 B

The attached sheet identifie. the Unit 1 and comon system pumps that are subject to the testing j requirements of Section XI, Subsection IWP H

Bi LEGEE:

Test Frequency h

H M = monthly Q

2M = every other month Y = 12 month Test Parameter g Pi = inlet pressure y Vv = vibration velocity

[ Q = flowrate Pd = discharge pressure N = speed Tb = bearing temperature L = level l

An og -

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ASME Section XI Valve Testing Program - Unit No.1 and Common Components ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: April 16, 1977 through December 16, 1983 NOTES:

1. The following sheets identify the unit 1 and common system valves that are subject to the testing requirements of Section XI, Subsection IWV. Valves in Code Class 1, 2 and 3 systems have been categorized in accordance with IWV-2110, subject to the exclusions of IWV-1300, using the following criteria.

a) The program has been limited to those Code Class 1, 2 and 3 valves that must function to prevent the occurrence of or mitigate the consequences of an analyzed accident contained in the FSAR.

b). Containment isolation valves are considered category A valves and are leak tested in accordance with the plant Technical Specification. Category A valves are exercised in accordance with IWV 3410, except where relief is requested. Containment isolation valves which are appendages of the containment vessel and are not connected to any other Code Class 1, 2 or 3 piping systems are not shown on code class drawings.

c) Code Class 1, 2 and 3 valves whose system safety function is adequately tested by the Technical Specifica-tion containment isolation valve testing program have also been omitted from the Section XI Valve Testing 7

s.

Program,

d. There are no partial stroke exercise tests in the program.

2. LEGEKD Test Type:

E = exercisc SP = relief valve setpoint verification L.= valve lineup check ,

LT = leak test Test Frequency:

M = monthly Q = quarterly R = refueling CS = cold shutdown

, Sy = 5 years

h S = startup 3 2W = every other week gH 2M = every other month O CU = core unload s-NOTE

Inservice valve testing at cold shutdown is defined as

Valve testing should commence not luter than 48 hra after shutdown and continue until complete or plant is ready to return to power. Completion of all valve '

testing :a not a prerequisite to return to power. 'Any testing not completed at one cold shutdown should be performed during the subsequent cold shutdowns to meet the code specified testing frequency.

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ASME CODE VALVES SYS FLOW DIAGRAM VALVE NO CLASS DWC DESCRIPTION VLV CAT TEST PROC REQUEST FOR RELIE1 FD/AF NF-39222 CV-31681 16 2 OR N N B SP-1102 E M #9 FD/AF NF-39222 CV-31682 16 B SP-1100 E M #9 T U FD/AF W-39222 AF-29-1 16 , C SP-1154(6) SP SY FD/AF NF-39222 AF-2922 16 12 m W N WWIM C

, ,y SP-1154 (6) SP SY FD/AF NF-39222 F-8-1 16 FW TO 11 SIM CEN CHECK C E . #27 FD/AF NF-39222 F-8-2 16 FW TO 12 S1H GEN CHECK C E - #27 FD/AF NF-39222 AF-16-1 16 SN GRunn TM P C SP-1101 E R f5, #12 FD/AF NF-39222 AF-16-2 16 -

1. 5, #12 GENERA FD/AF NF-39222 AF-15-1 16 AUX FW TO STEAM GEN C SP-1103 E R #5, #12 1i r nus r Ip. AUX FW TO STN GEN 12

FD/AF NF-39222- AF-15-2 16 r unt r C SP-1103 E R f5, #12-FD/AF NF-39222 AF-15-3 16 AUI FW TO S1M GEN 11 n

FD/AF NF-39222 AF-15-4 16 fHECK C SP-1101 E R f5. I12 FD/AF NF-39222 AF-15-9 16 C SP-1102 E M i5 FD/AF NF-39222 AF-14-1 16 N SUCTIN C - -

1. 27 FD/aF NF-39222 AF-15-10 16 1 AUX FW PHP DISCHARCE C SP-1100 E M #5 12 AUX FW PNP SUCTION FD/AF NF-39222 AF-14-3 16 CHECK

~ ~

RE G$ FD/AF NF-39222 AF-12-1 16 A W TO 11 S/G,' E C1.2 L S M

O$ PD/AF NF-39222 AF-12-2 16 AW to 12 S/G E C1.2 L S FD/AF NF-39222 AF-13-3 16 11 AW PMP DISCH E C1. 2. L S

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SP-1072-29B 7.7 R NF-39237 12 CNTMT SPRAY PMP E n #57,f5,f32 CS / CS-19 19 DSCH CHECK A ~

~ '^ LT R CS NF-39237 f MV-32103 19 1 C N SPRAY M SP-1137 E R #8 DISCH A SP-1072-29B LT R 12 CNTMT SPRAY PMP SP-1137 E R #8 CS NF-39237 MV-32105 19 DISCH A SP-1072-29A LT R CS NF-39237 CS-11 19 * * -

TO RWST RECIRC A SP-1072-29B LT R #58 CS NF-39237 CS-12 19 NR R g .h 29A' T R #58 CS NF-39237 CS 1 19 CA TO 11 CS PMP E C1.2 L S CS NF-39237 CS-32-2 19 CA TO 11 CS PMP E C1.2 L S CS NF-39237 CS-32-3 19 CA TO 12 CA PMP C1.2 E L S CS NF-39237 CS-32-4 19 CA TO 12 CS PMP E C1.2 L S f - .

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59. ~ REQUEST FOR RELIEF (con' t)

ALTERNATE INSPECTION (TESTING)

1. Valves listed as serving a pressure isolation function will be leak tested at function differential pressure during the daily reactor coolant inventory test. This test is described in Attachment 1. Estimated error is

'approximately 0.1 gallon / minute based on propagation of instrument error. This is an "on line" leak test which measures all sources of reactor coolant leakage, including leakage past pressure '_ solation valves into.

low' pressure systems. Typical. leakage rates measured are from 0.1 to 0.5 gallon / minute in each unit.

2. Following each refueling outage leakage testing of the pressure isolation valves is performed. The test method '

is. outlined below:

a. 32164, 32230, 32165, 32231

1. With RCS pressure at 2235 PSIG, . drain valve located downstream of 32164 and 32230 is opened, leakage C.7 is measured and-the~ drain valve reclosed.

y 2. Following a.1 above (RCS at 2235 PSIG) 32164 and 32230 are opened approximately 1/4 inch & the leakage lg ' through 32165 and 32231 is determined by monitoring the RHR system for any pressure increase.

b. 31447, 31449, SI-9-3, SI-9-4, SI-16-4, SI 5, SI-16-6, SI-16-7, SI-6-1, SI-6-3, and 32066

1. With RCS pressure at 2235, the RCS pressure boundary is extended do the second redundant' pressure isolation valve. (This is accomplished using steel tubing which connects the RCS to the drain valves between the first and second pressure isolation valves)

2. Following b.1 above flow and pressure instruments (F1-929 & Pl-929) are valved in to measure total leakage through SI-9-3, SI-9-4, SI-16-4, SI-16-5,, SL-16-6, and .SF16-7, 31447 and 31449.

3. Following b.1 above 11 & 12 accumulator levels are recorded. After a four hour period, the levels are again recorded. Any leakage past SI-6-1, SI-6-3, and 32066 will be reflected by a change in accumulator level (sensitivity of the level instruments are 4.46 GAL /%).

e

c. SI-9-1, SI-9-2, SI-9-5, SI-9-6

Following test condition b.1 above the RCS pressure boundary is returned to the first pressure isolation valve. Under this changed condition steel tubing is temporary installed to connect pressure and flow f, g instruments (F1-929 :. d Pl-929) to the low pressure side of SI-9-1, SI-9-2, SI-9-5 and SI.-9-6. F1-929 and

>; $ Pl-9.29 are then used to measure leakage through the valves listed above.

og. d. SI-6-2 and SI-6-4 Seat leakage through SI-6-2 and SI-6-4 is measured prior to placing the accumulators . in service.

SCHEDULE FOR IMPLEMENTATION Six months from submittal date of Revision 4.

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2

- , e SECTION 2 UNIT NO. 2 COMPONENTS

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This section contains a . description of our proposed program of inservice inspection and testing of components in Unit No. 2 of the Prairie Island Nuclear Generating Plant. This program conforms to the requirements of 10 CFR 50, Section 50.55a(g).

The information presented in this section follows the recommendations contained in a letter dated November 24, 1976 from Mr D L Ziemann, Chief, Operating Reactors Branch #2, Division of Operating Reactors, USNRC, and in a letter dated January 16, 1978 from Mr D K Davis, Acting Chief, Operating Reactors Branch #2. The program is updated as required by changes to Section 50.55a(g) published in the Federal Register on October 7,1979.

In ervice inspection and testing requirements are :pdated at 120 nonth intervals to conform to the latest edition and addenda of Section XI of the ASME Code referenced in paragraph (b) of 10 CFR 50, Section 50.55a. This manual will be updated each time changes are made to the ins:arvice inspection and testing program. Deviations from Code requirements are also documented for NRC Staff review in this manual.

The program description is arranged in the following manner:

Nondestructis e Examination Class 1 - Section 2.1.1 Class 2 - Section 2.1.2 Class 3 - Section 2.1.3 Pressure Tests - Section 2.2 Inservice Tests of Pumps - Section 2.3 Inservice Tests of Valves - Section 2.4 Deviations from Section XI - Section 2.5 Requirements Proposed changes to the Technical Specifications which implement this program on Unit No. 2 were submitted to the Commission on October 12, 1977.

A summary of these proposed changes is contained in Section 3 of this report.

System drawings showing ASME Code Classification boundaries are included in Section 4 of this report. These drawings define the pressure test boundaries and th'e Class 3 components subject to visual inspection'as part of the

nondestructive examination program.

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o O O ASNE Section XI Nondestructive Examination Program (Class 2) - Unit No. 2 ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: Ipril 21, 1978 through December 21, 1984 NOTES:

1.

The following tables identify the specific Class 2 components and parts to be examined. These tables can be directly correlated with Table IWC-2520 and Table IWC-2600 of Section XI and identify the examination method for each listed item. The tables ide' .tify the number of items required ten.(10) yearto be inspection examined- interval.

over a forty (40) year service lifetime, and the amount required for a The inspections that were performed during the first forty (40) months of operation are included, along with the corresponding percentage that was completed.

The tables also show the amount of items required to be examined during each period, and the percentage that will have been completed by the end of that period.

2.

The of scope of the inspection program for Class 2 components was based on the exemption criteria IWC-1220.

3.

to In accordance with the requirements of IWC-2411 the nondestructive examinations were selected g . so that the total examinations completed over forty (40) years will be 1007, of the required ro examinations of the system or portions of the systems with a single stream or be equivalent to A- having system.performed 100% of the required exami. nations in one of.the streams of a multiple stream The selection 4.

and design of valve and not on the total number of certain size valve bonnet bolts per Repairs and addenda will be performed of the in accordance ASME Code, Section XI. with the applicable requirements of the latest edition However, if rules for a particular repair are not specified in Section XI, the original design specification and Construction Code of the component or system, entirety or later editions or portions thereof, of thebeConstruction may used. Code or ASME Code Section III, either in their LEGEND:

Examination method:

V -

visual U.T. -

ultrasonic R.T. -

radiography

, S -

D surface examination, either liquid penetrant or magnetic particle Inspection Period:

h og ONE IWO December 21, 1974 to April 21, 1978 April 21, 1978 to August 21, 1981

, THREE -

August 21, 1981 to December 21, 1984

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ASME Section XI Nondestructive Examination Program (Class 3) - Unit No. 2 ASME Code Edition and Addends: 1974 Edition through and including Summer 1975 Addenda Program Period: April 21, 1978 through December 21, 1984 NOTES:

1. The classification diagrams identify the systems that are required to be examined in accordance with IWD-2000. Refer to Section 4 of this report.

2. The scope of the inspection program for Class 3 components is based on the classification of the plant's inspection boundaries and exemptions as allowed for in IWD-2600 and IWD-5200. The inspection program is in accordance with 14D-2400 (Inspection Schedule),

m 3. Visual examination will be conducted for evidence of component leakage, structural distress, or

.g corrosion when the system is undergoing either a system inservice test, component func tional o test, or a system pressure test.

N

4. Supports and hangers for components will.be visually examined to detect any loss of support capability or evidence of inadequate restraint.

5. Repairs will be performed in accordance with the applic'able requirements of the latest edition and addenda of the ASME Code,Section XI. However, if rules for a particular repair are not specified in Section XI, the original design specification and Construction Code of the component or system, -or later editions of the Construction Code or ASME Code Section III, either in their entirety or portions thereof, may be used.

LEGEND:

Inspection Period

• [ g - ONE -

December 21, 1974 to April 21, 1978 q$ TWO -

April 21,1978 to August 21, 1981 ggm THREE - August 21, 1981 to December 21, 1984 og

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ASME Section XI Pump Testing Pzugram - Unit No. 2 ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: December 21, 1979 through December 21, 1984

' The attached sheet identifies the Unit 2 system pumps that are subject to the testing requirements of Section XI Subsection IWP.

LEGEND:

4 Test Frequency M = monthly 2M - every other month

< - ta A Test Parameter -

Pi = inlet pressure Vv = vibration velocity Q = flowrate Pd = discharge pressure N = speed

Tb = bearing temperature L = level r

25 S

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ASME Section XI Valve Testing Program - Unit No. 2 ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: December 21, 1979 through December 21, 1984 NOTES:

1.

The following sheets identify the Unit 2 system valves that are subject to the testing requirement of Section XI, Subsection IWV.

Valves in Code Class 1, 2 and 3 systems have been categorized in accordance with IWV-2110, subject to the exclusions of IWV-1300, using the following criteria:

a) The program bas been limited to those Code Class 1, 2 and 3 valves that must function to prevent the occurrence of or mitigate the consequences of an analyzed accident contained in the FSAR.

b) Containment isolation valves are considered category A valves and are leak tested in accordance with.

the Plant Technical Specification. Category A valves are exercised in accordance with IWV 3410, except where relief is requested. Containment isolation valves which are appendages of the containment veasel f* and are not connected to any other code class 1, 2 or 3 piping systems are not shown on code class draw-ings. '

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2. There are no' partial stroke exercise tests in the program, LEGEND .

Test Type:

E = exercise SP = relief valve setpoint verification L = valve lineup check LT = leak test Test Frequency:

D = daily CS = cold shutdown M = monthly CU = core unload 5y = 5 years Q = quarterly S = startup R = refueling 2W = every other week

CS = cold shutdown 2M = every other month

! f[g NOTE: Inservice valve testing at cold shutdown is defined as: Valve testing should commence not later than 48 0m hours after shutdown and continue until complete or plant is ready to return to power. Completion of all lEsn valve testing is not a prerequisite to return to power. Any testing not completed at one cold shutdown l 0 @l should be performed during the subsequent cold shutdowns to meet the code specified testing frequency.

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L AStiE CODE VALVES SYS FLOW DIAGRAM VALVE NO. CLASS IMG DESCRIPTION VLV CAT TEST PROC Pf RE F SI X-HIAW-1001- 6 MV-32177 I 13 2 SAF INS REAC VSL INJ SP-2137 E R #8 ISOL A SP-2072-28A LT R SI X-HIAW-1001-6 MV-32176 33 2 REAC SM MJ m C1.1. M-2 L S LEC ISOL A SP-2072-28B E,LT R #57 SI X-HIAW-1001-6 ONTAMMENT SW B SP-2137 E R #8, #16 MV-32178 33 ISOL A-1 A SP-2072-30A LT R 21 CONTAINMENT SUMP B SP-2137 E R #8, #16 SI X-HIAW-1001-6 MV-32179 33 ISOL A-2 A SP-2072-30A LT R SI X-HIAW-1001-6 CV-31554 N/A 2 CN NMEN SOL A SP-2072-31 IT R 0 ACC SI X-HIAW-1001-6 CV-31244 N/A 2 A SP-2072-31 R SUPPLY TO 21 ACC E R #57 SI X-HIAW-1001-6 CV-31511 33 2 ISOL A SP-2072-31 LT R N SUPPLY TO 22 ACC E R #57 SI X-HIAW-1001-6 CV-31512 33 2 ISOL A SP-2072-31 L1 R 2 REAC VSL INJ FR SP-2167 L CS no p SI X-HIAW-1001-6 MV-32168 33 ~~~

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SYS FLOW DIAGRAM VALVE NO. CLASS DWG DESCRIPTION VLV CAT TEST PROC pf f fp SP-2070 LT R SI X-HIAW-1001-6 2SI-6-1 33 22 ACC DISCH CHECK A S P-2 001-AA LT D #59 ep-2070 c1_ ' LT R l SI X-HIAW-1001-6 2SI-6-2 33 22 ACC DISCH CHECK A SP-40U1'-AA LT D #59 co ?n7n LT R SI '/-HIAW-1001-6 2SI-6-3 33 21 ACC DISCH CHECK A SP-zoul-AA 59 LT D SP-2070_r1 ' vm o SI X-HIAW-1001-6 2SI-6-4 33 21 ACC DISCH CHECK A

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LO HEAD SI TO RX VSL SP-2070 ym n SI X-HIAW-1001-6 2SI-9-3 33 CHECK A SP-2001-AA #59 vm n SI X-HIAW-1001-6 2SI-9-4 33 LO H M SI TO M M SW2070 M n CHECK A SP-2001-AA LT D #59

,N LO HEAD SI TO RX VSL SP-2070 LT R e SI X-HIAW-1001-6 2SI-9-5 33 CHECK A SP-2001-AA TT D #59 E LO HEAD SI TO RX VSL SP-zu/U -T5 - n SI X-HIAW-1001-6 2SI-9-6 33 puppg A SP-2001-AA LT D #59 SP-2070 T.T R SI X-HIAW-1001-6 2SI-16-4 33 SI TO LP B CL CHECK A SP-2001-AA LT D #59 RP-2070 T.T R SI X-HIAW-1001-6 2SI-16-5 33 SI TO LP A CL CHECK A SP-2001-AA #59 LT D RP-2070 Tm R SI X-HIAW-1001-6 2SI-16-6 33 SI TO RX VSL CHECK A SP-ZUUl-AA [.. p #59 RP-?O70 - LT n SI- X-HIAW-1001-6 2SI-16-7 33 SI TO RX VSL CHECK A SP-zuul-AA #59 t.7, 3 d

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ASME CODE VALVES SYSTD1 FLOW DIAGRAM CLASS TEST REQUEST FOR VALVE NO. '

TEST DWG RELIEF CAT TYPE FREQ FD-AF NF-39223 CV-31684 22 RD AFWP OIL CLR CLC 38 ~

WATER INLET FD/AF NF-39223 CV-31683 38

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FD/AF NF-39223 2AF-29-1 38 21 AUX FW PMP SUCT RELIEF C SP-2154(6) SP SY FD/AF NF-39223 2AF-29-2 38 22 AUX FW PMP SUCT RELIEF C SP-2154(6) SP SY FD/AF NF-39223 2FW-8-1 38 FW TO 21 Sm GEN CHECK C 4

1. 27 FD/AF NF-39223 2FW-8-2 28 FW TO 22 Sm GEN CHECK C - -

1. 27 FD/AF NF-39223 AUX FW TO 21 STEAM GEN-AF-16-4 38 ERATOR CHECK C SP-2101 E R #5, #12 FD/AF NF-39223 AF-16-3 38 ^" ~

C TO CHE SP-2101 E R #5, #12 FD/AF NF-39223 AF-15-7 38

" AUX FW TO STM CEN 21 CHECK C

. SP-2103 E R #5, #12 i FD/AF NF-39223 AF-15-6 38 C AUX FW TO STM GEN 22 CHECK C SP-2103 E R #5, #12 FD/AF NF-39223 AF-15-8 38 AUX FW TO STM CEN 21 CHECK C SP-2101 E R #5, #12 FD/AF NF-39223 AF-15-5 38 AUX FW TO S m CEN 22 CHECK C SP-2101 E R #5, #12 FD/AF NF-39223 AF-15-12 38 22 AUX FW PMP DSCH CHECK C SP-2102 E M #5 FD/AF MF-39223 AF-14-7 38 22 AUX FW PMP SUCT CHECK C - -

1. 27 FD/AF NF-39223 AF-15-11 38 21 AUX FW PMP DSCH CHECK C SP-2100 E M #5 FD/AF NF-39223 AF-14-5 38 21 AUX FW PMP SUCT CHECK C -

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1. 27 D  : FD/AF NF-39223 AF-12-3 38 AFW TO 22 S/G E- C1.2 3 L S

$ FD/AF NF-39223 AF-12-4 38 AW TO 21 S/G E C1.2 L S

• FD/AF NF-39223 AF-13-5 38 21 AFW PMP DSCH E Cl.2 L S

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ASME CODE VALVES SYSTEM FLOW DIAGRAM VALVE NO. -

DESCRIPTION VLV TEST PROC D

FR F R REL EF l CAT CA NF-39252 CV-31939 18 B SP-2090 C ST IE S E M #18 CA NF-39252 CV-31940 22 RA SU 18

,pE S B SP-2090 E M #18 CA NF-39252 2CA-ll-1 18 C S EF C SP-2153 E Q #5 CA NF-39252 2CA-7-1 18 VACUUM BREAKER AT STANDPIP s C SP-2152 E CS #17 CA NF-39252 2CA-7-2 18 VACUUM BREAKER AT STANDPIP s C SP-2152 E A #17 CA NF-39252 2CA-1-1 18 CV-31939 INLT ISOL E C1.2 L CS CA NF-39252 2CA-1-2 18 CV-31939 OUTLET ISOL E C1.2 L CS y CA NF-39252 2CA-1-3 18 CV-31940 INLET ISOL E C1.2 L CS

'n CA RF-39252 2CA-1-4 18 CV-31940 OUTLET ISOL E C1.2 L CS

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62. REQUEST FOR RELIEF ASME COMPONENT FUNCTION Code Vlv Class Cat React Val Inj Fr RH MV-32167 Low head SI to reactor vessel. 2 A React Vsl Inj Fr RH MV-32168 Low head SI to reactor vessel. 2 A CODE REQUIRDIENT The valves will not be exercised as required by IWV-3520.

g BASIS la These valves are normally closed. They open automatically on receipt of an SI signal.

Reactor operation with these valves open is possible, but closed they afford an additional degree of protection for low pressure RHR piping. During periodic exercising of these valves, both check valves would have to be stuck open a significant amount to threaten RHR piping with overpressurization. While this possibility is renote we will revise our valve testing program to eliminate this potential hazard by scheduling tests for cold shutdown outages when the reactor coolant system is depressurized and cooled down.

ALTERNATE INSPECTION (TESTING)

These valves will be stroked each cold shutdown.

SCHEDULE FOR IMPLEMENTATION Six months from submittal date of Revision 2.

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