ML20077N445

Forwards Request for Relief Re Unit 1 Inservice Insp & Testing Program to Complete Listed Program Requirements. Justification Provided.Extension Until 1985 Outage (Cycle 10) Requested

ML20077N445
Person / Time
Site:	Prairie Island
Issue date:	08/26/1983
From:	Musolf D NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
References
TAC-52405, NUDOCS 8309130100
Download: ML20077N445 (15)

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• Northem States Power Company 414 Nicollet Mall Minneapohs. Minnesota 55401 Telephone (612)330 5500 August 26, 1983 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR CENERATING PLANI Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 First Ten Year ISI/IST Program Completion Unit 1 Request For Extension Attached are forty copies of a request for relief related to the Unit 1 Inservice Inspection and Testing (ISI/IST) Program. This request is submitted in accordance with 10 CFR 50, Section 50.55a(g)(5)(iii) . A fee determination form and check in the amount of $4,000.00 is attached.

Northern States Power Company is submitting this request for time extension in completing the first ten year inservice inspection and testing program requirements. The two program requirements requiring extra time are:

1. ISI - incpection of the reactor vessel welds and areas requiring the use of the reactor vessel inspection tool or lower internals removed.

2. IST - performance of the hydrostatic tests for class 1, 2 and 3 equipment as noted on pages 1.2-1 of the IST program.

All the other cequirements for Unit 1 in the ISI/IST program will be completed by the end of 1984.

Prairie Island Unit 1 ten year outage is scheduled to start Jaauary 5, 1985 and Unit 2 August 16, 1985. This schedule places the start date of Unit I ten year outage 29 days over the time allowed by ASME Code Section XI for completion of the inspection program. The licensee requests an extension of the grace period for the completion of the program until the 1985 outage for Unit 1 (Cycle 10). No extension is being requested at this time for Unit 2 because the outage is still within the ten years plus the allowed grace period of one year for the program. The licensee requests and needs the extension to be granted because:

8309130100 830826 PDR ADOCK 05000282 PDR G

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NORTHERN CTATEC POWER COMPANY Dir of NRR August 26, 1983

.Page 1

1. The time extension interval requested is minimal and it is for only two areas of the program.

2. Those inspections needing the time extension are those which require the core to be unloaded and/or an extended outage to complete.

3. - Monticello's outage to replace the recirculation piping is scheduled from January 28, 1984 to August 14, 1984. NSP does not schedule two large unit outages at the same time. If Prairie Island would do the ten year outage for Unit 1 in 1984, it would overlap with Monticello's outage causing two units to be out of service simultaneously. The average cost for one of the units to be out of service is approximately

$200,000 per day. The scheduling of a second imit outage at the same time would as a minimum double the cost per day. The current schedule has Unit 1 back on line before Monticello starts its' outage.

4. The available manpower resources would be exceeded by having two units in major outages at the same time.

The specific sections of the ISI/IST program for which extension is being requested are:

1. ISI - Items Bl.1, Bl.2, Bl.3, Bl.4, Bl.6, Bl.9, Bl.12, Bl.14, Bl.15, Bl.17, Bl.19 and B4.1 2.- IST - The ten year hydrotests as noted on page 1.2.1 of the ISI/IST manual.

Please contact us if you have any questions related to our request for relief from the requirements of our ASME Code Section XI Inservice Inspection and Testing Program.

d Ows Dav d Musolf Manager - Nuclear Support Se ices cc: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC G Charnoff Attachment

REV 10 Instructions for Entering i l

Insert pages in the Prairie Island's 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 as follows.

• Remove Page Insert Attached Revised Pages i i 111 111 1.1.1-2 1.1.1-2 1.1.1-3 1.1.1-3 1.1.1-4 1.1.1-4 1.1.1-5 1.1.1-5 1.1.1-6 1.1.1-6 1.1.1-14 1.1.1-14 1.2-1 1.2-1 1.5-48 1.5-48 1.5-49 (new) 1.5-49A (new)

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NORTHERN STATES POWER COMPANY .

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. PRAIRIE ISLAND NUCLEAR GENERATING PLAIR

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DOCKET NOS. 50-282 LICENSE 110S. DPR-42 ~

50-306 DPR-60 AS?iE CODE SECTION XI . INSERVICE ~ INSPECTION AND TESTING PROGRAll 7

AND.

INFOR!!ATION REQUIRED FOR NRC REVIEW OF REOUESTS FOR RELIEF ' FR0!i

-AS!!E CODE SECTION XI REQUIREMEtES Y

SUBMITTED: ~ February 1, 1978~ REVISED: Revision i 1

September 15, 1978

Revision 2'-

June 8, 1979

[

Revision 3-September 19, 1979 Revision 4

[ April 17, 1980 Revision 5 September 3, 1980

!, Revision 6 i- July 31, 1981 Revision 7

, December 23, 1981-Revision 8 g April 19, 1983 Revision 9

[_ June 24, 1983 b Revision 10 I

'd August 26, 1983 i

,._.u... .. .s._..._..... . _ . . . _ , . , , , . _ . ~ ~ . . . , - _ . , _ _....,,..,.,..m.--..-_w. - , - . . . . , _ , . . . . .

RECORD OF REVISIONS Page No Revision No Page No Revision No I] Cover 10 1.5-6 Original ii 4 1.5-7 1 111 10 1.5-7A 1 iv 9 1.5-7B 2 1-1 4- 1.5-8 thru 1.5-9 Not Used

'1.1.1-1 4 1.5-10 1 1.1.1-2 thru 1.1.1-6 10 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 1.1.1-13 Original 1.5-14 thru 1.5-15A 8 1.1.1-14 10 1.5-16 1 1.1.1-15 thru 1.1.1-17 Original. 1.5-17 Original 1.1.1-18 1 1.5-18 1

1. 1. 1-19 Original 1.5-18A 1

,1.1.1-20 1 1.5-19 Original 1.1.1-21 thru 1.1.1-25 Original 1.5-20 1 1.1.1-26 thru 1.1.1-28 6 1.5-21 Not Used 1.1.1-29 thru 1.1.1-33 Original 1.5-22 thru 1.5-23 Original 1.1.1-34 '

9 1.5-24 2 1.1.1-35 original 1.5-25' 6 1.1.1-36 6 1.5-26 Not Used 1.1.1-37 thru 1.1.1-39 Original 1.5-27 thru 1.5-28 Original 1.1.2-1 4 1.5-29 8 1.1.2-2 thru 1.1.2-27 6 1.5-30 Original 1.1.3-1 4 1.5 8

% 1.2-1 10 1.5-32 thru 1.5-34 1 1.3-1 4 1.5-34A 1

! 1.3-2 1 1.5-35 Original 1.4-1 4 '

1.5-36 6 1.4-2 1 1.5-37 thru 1.5-39 Original 1.4-3 thru 1.4-4 2 1.5-40 1 1.4-5 4 1.5-41 Original 1.4-6 1 1.5-42 1 1.4-7 thur 1.4-8 4 1.5-43 2 1.4-9 2 1.5-44 thru 1.5-46 Not Used 1.4-10 1 1.5-47 Original 1.4-11 7 1.5-48 thru 1.5-49 10 1.4-12 2 1.5-49A 10 1.4-13 Not Used 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 l 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 8 l 1.4-22 1 1.5-61 thru 1.5-62 Original

.1.4-23

• 4 1.5-63 6 l 1.4-24 thru 1.4-34 1 1.5-64 thru 1.5-68 1 1.5-1 2 1.5-69 2 l 1.5-2 1 1.5-70 4

! 1.5-3 8 1.5-3A 8 1.5-4 thru 1.5-5 8 1

iii Revision 10 L Augus,t__26_, M83

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3 m, NORTHERN STATES POWER CO.

TABLil 1.1 ORA!RIE ISLAND UNIT 1 T E t3 YEAR t ra f ER V AL I t4 SPEC T I Ota SUMM AR Y l' GE 1 OF _L ,

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LONGITUDINAL WELDS NONE - - - - -

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TABir~ 1.4 PRA!RIE !$ LAND Ur!!T 1 TEM (CAR INTERVAL I NSpr C T I f5N

SUMMARY

MtHI iml: PIPINt: PRESSURE BOUNDARY liXMI. GM0rGT Oft SYSTIN, 1UTAI. INSPIX i

Calli- AND 1113OlllT10N 01: rO.PLII !IDlNilFICATION IIW IINATIW Tim TW M NM l

IE mnY iTIN 10 BE EXMflNED U '

M1XNT AND IiX11NT SYSil}I NIMBER PERG NI RI)nRKS film p,pinn B4.1 B-F SAFE-END TO PIPING AND SAFE-END IN BRANOI PIPING WELDS I

RELIEF No. 46 RFACTOR YESSEL (6)

REACTOR CORE COOIANT SYSTEMS 4 S-UT RCC-A-1 S.E. 1 WELD 100% ONg (29.RC-IA) 25 180[

RCC-B-! S.E. 1 WELD 100% 1Wo 0, (29.RC-18) 50 l RCC-A-14 S.E. I WELD 1001 111REE 120 (27.5-RC-3A) !5 RCC-B-14 S.E. I WELD 100% 300, 100 111MEE (27.5-RC-38) l SAFETY INJECTION SYSTEMS 2 S-UT g LOOP A, WELD 2 2

• S.E. I WELD 100% ONE 260 (4-RC-14A) 50

!LOOPB. WELD 2

! S.E. I WELD 100% 111 reg 80,' 100 V (4-RC-148) i f STEAM CENERATOR NO. 11 (2) I Y I

! Y REACTOR CORE C00lANT SYSTFM 2 S-UT I RCC-A-5 S.E. I WELD 100% ONE CUBICLE A (31-RC-2A) 50 i I RCC-A-4 S.E. I WELD 100%

I.

11 TREE CUBICLE A (29-RC-IA) 100 STEAM GENERATOR NO. 12 (2)

REACTOR CORE CUOIANT SYSTEM 2 S-UT I WELD 1WO CUBICLE B (31-RC-2B; 50 '

lRCC-B-5S.E. 100%

g RCC-B-4 S.E. 1 WELD 1007 111REE CUBICLE B (29-RC-18) ILO 2

i j PRESSURIZER (5)

! SAFE 1Y LINES 2 S-UT 8010A, 1 S.E. I WELD 1001 ONE TOP OF PZR (6-RC-20A) 20 80108, 1 S.E. I WELD 100% ONE 10P OF PZR (6-RC-20s) 40 j SURGE LINE I S-UT WELD 6. S.E. 1 WELD 100% Iwo 60 4

807 0F PZR (10-RC-4) i RELIEF LINE I S-UT WELD 1, S.E. I WELD 1001 111REE . TOP OF PZR (3-NC-21) 80 4

l gg SPRAY LINE I S-UT WELD 29, S.E. I WELD 100% 111REE TOP OF PZR (3-RC-5) 100 j g4 -l (4-RC-5) w O

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ASME Section XI Pressure Testing Program - Unit No. I and Common Components ASME Code Edition and Addenda: 1974 Edition through.and including Summer 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 follows:

ASME TEST TEST TEST SPECIFICATION REQUEST FOR RELIEF CODE CLASS TYPE FREQUENCY l Leakage Refueling IWB-5210(a). #20, #60 IWB-5221 g

IWA-5000 1 Hydrostatic 10 years, IWB-5210(b) #20 i #42 IWB-5222 IWA-5000 .

2 Pressure Test 3 1/3 years IWC-2412 #19, #20, #29 IWC-2510 IWC-5210 2 Hydrostatic Test 10 years IWC-2412 #19, #20, #29 , #42 IWC-2510 IWC-5210 g 3 Pressure 10 years IWD-2410(b) #20, #28, #30,'#31

1. 42 g@8 3

m b

g ~s <~s, f "y/ N' ~'

40. REOJ ST FOR RELIEF ASME C0f!POMENT FUNCTION Code Viv Class Cat 12,22, Diesel Cooling Water Pump Remove heat from components that must function 3 -

during accident conditions.

CODE RE0llIRE!!EFTP Inlet pressure will not be used to evaluate the condition of the pump as required by IUP-3;10 and 3210.

BASIS The pump suction is located in the cooling water intake bay and suction pressure indication is not available.

ALTERt! ATE IIISPECTI0t1 (testing)

Intake bay level will be factored into the dif ferential pressure data used in the pump test.

L

• SCilEDtiLE FOR IMPLE11ENTATION April 16, 1977 i$

5E

~

^ ~-

.. 42. REQUES'Fr0R RELIEF -

COMPONENT OR ITEM' . . CODE PROGRAM -CODE' -EXAM.

CLASS TABLE ITEM CATEGORY'. -

LO!!GITUDI!!AL AND CIRCUMFEREPRIAL SilELL WELDS 1 1.1 'Bl.1 'B-A '

IN CORE REGION.

LONGITUDINAL AtlD CIRCUHFEREtGIAL WELDS IN SilELL -1 1.1 Bl.2 - -B-B.

(OTHER TilAN TilOSE OF-CATEGORY B-A AND B-C A!!D !!ERIDIONAL AND CIRCUHFEREttfIAL SEA!!

WELDS IN BOTTOM HEAD AND CLOSURE HEAD (OTilER TilAN T110SE OF CATEGORY- B-C) .

VESSEL-TO-FLANGE AfD llEAD-TO-FLANCE 1 1.1 Bl.3. B-C CIRCUtlFEREffrIAL WELDS.

PRI!!ARY 130ZZLE-TO-VESSEL WELDS' AND 1 1.I B1.4 B-D t10ZZl.E INSIDE RADIUSES.

VESSEL PENETRATIONS, INCLUDING CONTROL ROD DRIVE 1.1 Bl.5 B-E

(

1 AND INSTRUt!ENTION PENETRATIONS.

.N07.ZLE-TO-SAFE END WELDS. I 1.1 Bl.6 B-F LIGA!!E!TfS liETWEEN THREADED STUD 110LES. I 1.1 Bl.9 B-G-l' ItTTEGRALI,Y UELDED VESSEL SUPPORTS. .I 1.1 Bl.12 B-Il VESSEL CLADDING. I 1.1 Bl.14 B-I-l VESSEI. INTERIOR. I 1.1 Bl.15 B-N-1 RETIOVAllLE CORE-SUPPORT STRUCTURES. I 1.1 B1.I7 B-N-3 EXEt!PTEI) CortPONE!!TS. I 1.1 Bl.19 B-P SAFE-END TO PIPIllG AND SAFE-END IN BRANC11 1 1.4 B4.1 B-F PIPIrlG UELDS REACTOR VESSEL.

E a

42. REQmT FOR RELIEF (Cont'd) '

~

. C0ttPONEtR OR ITEM ' CODE PROGRAtl ' TEST '

, CLASS 'PAGE '*

FREQUENCY ,

ilYDRO STATIC TESTS' 1,2,& 3 1.2-1 10 years CODE REQUIREMEM1'

.,These tests will be completed within the interval of 10 years plus 'l year allowed extension.

BASIS The timing and scheduling to complete the Prairie Island Unit l'first Ten-Year ISI/IST Program exceeds the eleven year time frame allowed by the Code. ~ALdetailed basis for this request is contained in NSP letter dated 8/26/83.

AI. TERNATE The tests will be done during the 10 year outage for Unit 1 schedule to start in . January 1985.,

6 SCilEDUI.E FOR IttPLEMENTATION i.

y Three months from the submittal date of-August 26, 1983.

o

. . _ ._ _