ML19270H010

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Submits Info Re Facility Feedwater Line Design, Fabrication, Insp & Operating History
ML19270H010
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/19/1979
From: Mayer L
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 7906220357
Download: ML19270H010 (20)


Text

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NSD NORTHERN STATES POWER COMPANY M IN N E A PO U S. MIN N E SOTA 55408 June 19, 1979 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Information on Prairie Island Feedwater Lines In a letter dated May 25, 1979 from Mr Victor Stello, Director, Division of Operating Reactors, USNRC, we were informed of a recent discovery of feedwater line cracking at another f acility and were requested to submit information related to the Prairie Island feedwater line design, fabrication, inspection, and operating history for NRC Staff review. This letter provides a response to Mr Stello's request. The following information is provided:

Design

1. Provide as-built piping or isometric drawings of the feedwater line to steam generator sparger within containment. Show details of the design such as dimensions, pipe schedule, support type and locations, pipe restraints, and valve (s).

Response

One set of drawings is included as Attachment (A). The drawings in Attachment (A) are current as of the date of this letter. Because the drawings are revised from time to time, they should be used with caution.

2. Provide the results of any stress or fatigue analyses which was performed for this system.

Response

The feedwater piping to nozzle weld region has been reanalyzed by the Prairie Island architect-engineer. The results will be forwarded for Staff review when the report is completed. Review of the original stress analysis indicates it did not reflect the as-built configuration of this region.

Reanalysis has shown allowable stresses are not exceeded. 2318 318 7906220357

NORTHERN STATES POWER COMPANY Director of Nuclear Reactor Regulation Page 2 June 19, 1979 Fabrication History

1. Supply a list of the materials for the steam generator sparger, steam generator feedwater nozzles, and feedwater piping within containment.

Response

Steam Generator Sparger SA 106 Gr B Steam Generator Feedwater Nozzles SA 508 C1 2 Feedwater Nozzle - Feedwater piping spool piece

  • Reference Dwg NF 39273-1 and NF 39274-1 (see Attachment A)
    • Reference SS-M368 and SS-M327 (see Attachment B)
2. Provide the details of the welding process (co) used to make the nozzle-to-pipe, pipe to sparger and piping welds. Include details of welding such as preheat, joint configuration (include with or without backing ring), and post weld treatment, if any.

Response

See Attachment (C). One set of documentation is included.

a. Welding Process - NAVC0 Procedure ITH1-1 Rev. I for Field Welds in piping and nozzle-to-pipe welds only.
b. Preheat - 200 degress ? minimum (piping velds).
c. Joint Configuration - NAVC0 sketches listed above.
d. Post Weld Heat Treatment - Piping only, per NAVC0 procedure FE-6 plus PWHT Charts. This is typical and also reported on each Weld Data Sheet for Field Welds. Shop weld filler metal is quoted in shop weld QA Data Sheets attached to Shop Fabrication Drawings. Stress Relief is included in the QC Data Sheets (sign off & Procedure ID).
e. There is no pipe to sparger weld; this is a slip fit.
3. Provide the NDE performed during and af ter fabrication of the weld joints requested in question 2.

Response

a.

b.

visual for fit up dye penetrant (final) 2 ]h jlh

c. radiograph (final)

NORTHERN STATES POWER COMPANY Director of Nuclear Reactor Regulation Page 3 June 19, 1979

4. Provide the code edition to which the feedwater piping system was fabricated.

Response

System was fabricated to ANSI B31.1 1967 Edition.

5. State the fracture toughness requirements, if any, for the feedwater piping system.

Response

There were no fracture toughness requirements for the feedwater piping system.

Preservice/ Inservice Inspection and Operating llistory

1. State whether the feedwater system welds received a preservice inspection in accordance with ASME B&PV Code,Section XI.

Response

Unit 1 A preservice examination was performed on circumf erential butt welds on the feedwater lines from the turbine building wall to the containment penetration. Examinations were performed in accordance with 1971 Edition, including the Summer 1971 Addenda, of ASME B&PV Code, of the feedwater butt welds in this area, with the exception of three welds on loop A and two welds on loop B that were inaccessible. A preservice examination was not performed on the pipe to steam generator nozzle welds.

Unit 2 Same as Unit 1; except, five welds on loop A and one weld on loop B were not examined due to inaccessibility.

2. Provide the extent of inservice inspection performed on the feedwater pipe to steam generator nozzle welds. Include the results of the examinations, any corrective actions taken and causes of any failures.

Response

Unit 1 Visual, ultrasonic, and radiographic examinations were performed on the feedwater pipe to steam generator nozzle welds during a veckend outage on June 9 and 10,1979. The visual examinations revealed no 2 b

NORTHERN STATES POWER COMPANY Director of Nuclear Reactor Regulation Page 4 June 19, 1979 apparent discontinuities. The only indications detected by ultrasonic examination were geometric reflectors from the counter bore on loop B.

The radiographic examination revealed the same indications as seen on the construction radiographs, i.e. porosity, with no indications of cracking in the pipe taper area or around the weld. No corrective action was needed or taken.

Unit 2 Inservice examinations have not been performed on the feedwater pipe to steam generator nozzle welds. See the answer to "3".

3. Provide the schedule and extent of inservice inspection for the feecwater system for the next inspection interval.

Response

The tables in Attachment D indentify the schedule and extent of inservice examinations on the feedwater system for the first ten year inspection interval. The tables identify the total number of items requiring exami-nation, the amount required during the first ten year interval, the in-spection period that they will be or have been examined, and tho examinations that have been completed. For those examinations that have been completed, the weld or hanger number and the year-report number is given in the remarks column.

Unit 1 Du: 'ng the Prairie Island Unit I weekend outage on June 9 and 10, 1979, a visual and ultrasonic examination was pc-formed on the feedwater system piping welds from the last check valve in both systems to and including the pipe to steam generator nozzle welds, with the exception of the chect volve to elbow weld on laop B that was ene.apsulated. In addition, a radiographic examination was performed on both pipe to steam generator nozzle welds. The auxiliary feedwater piping walds were also examined from the. 'ast check valve to the sweep-o-let connection weld with the feedwate lines. There were no indications of degradation to these systems.

Unit 2 For Prairie Island Unit 2, we are planning to examine the feedwater pipe to steam generator nozzle welds during the next refueling outage.

b J2}

NORTHERN STATES POWER COMPANY Director of Nuclear Reactor Regulation Page 5 June 19, 1979

4. Provide any history of water hammer or vibration in the feedwater system anddesign changes and/or actions taken to prevent these occurrences.

Response

See Attachment E.

5. Provide a description of feedwater chemistry controls and a summary of chemistry data.

Response

See Attachment F.

Please contact us if you have questions related to this information.

Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/ak cc: J G Keppler (w/o Attachment A and C)

G Charnoff (w/o Attachment A and C) e '

2318 :22

Attachment A The following prints are provided for Unit 1:

XH-106-130 Isometric of Unit 1 Feedvater Piping NF-39273-1 Physical Drawing of Unit 1 Feedwater Piping NF-39273-2 Physical Drawing of Unit 1 Feedwater Piping NF-39273-4 Physical Drawing of Unit 1 Feedwater Restraint NF-39273-5 Physical Drawing of Unit 1 Feedwater Restraint NF-39273-8 Physical Drawing of Unit 1 Feedwater Restraint NF-39273-9 Physical Drawing of Unit 1 Feedwater Restraint NF-39273-10 Physical Drawing of Unit 1 Feedwater Restraint NF-39316-2 Physical Drawing of Unit 1 Auxiliary Feedwater NF-39316-3 Physical Drawing of Unit 1 Auxiliary Feedwater NF-39326-2 Physical Drawing of Unit 1 Cleaning System NF-38422-3 Physical Drawing of Unit 1 Miscellaneous Structures NF-38422-4 Physical Drawing of Unit 1 Miscellaneous Structures NF-38422-5 Physical Drawing of Unit I hiscellaneous Structures NF-38422-6 Physical Drawing of Unit 1 Miscellaneous Structures NF-38422-7 Physical Drawing of Unit 1 Miscellaneous Structures

r-38422-8 Physical Drawing of Unit 1 Miscellaneous Structures NF-38422-9 Physical Drawing of Unit 1 Miscellaneous Structures NF-38422-33 Physical Drawing of Unit 1 Miscellaneous Structures NF-38425 Physical Drawing of Unit 1 Miscellaneous Structures XH-106-6104 Through XH-106-6165 Restraint and Hanger Drawings for Unit 1 Feedwater Piping XH-106-130 Drawing of Anchor Elbow XH-106-131 Drawing of Anchor Elbow XH-80-1 Drawing of Check Valve XH-80-2 Drawing of Check Valve The following prints are provided for Unit 2:

X-HIAW 1106-246 (NAVC0 A-7047)

-1664 FWH - 53 2318 23 1665 1667 FWH - 54 1668 1669 3414 FWH - 58 3415 3416 3417 FWH - 59 3418 3419 3421 FWH - 60 3422 3423 A-1

Attachment A (contd.)

X-HIAW 1106-3425 M - 61 3426 3427 3428 3429 3430 M - 62 3431 3432 3433 3434 3435 M - 63 3436 3437 3438 3439 3440 M - 64 3441 3442 3443 3444 3445 M - 65 3446 3447 3448 3449 3450 M - 66 3451 3452 3453 3455 M - 67 i'5 2318 .24 3458 3459 3460 M - 68 3461 3462 M - 69 3463 3464 3465 3467 3467 3468 FWH - 70 A-2

Attachment A (contd.)

X-HIAW-1106-3469 FWH - 71 3470 3471 3472 3473 3555 FWH - 72 3556 3557 FWH - 73 3558 3559 FWH - 74 3560 3561 FWH - 75 X-HIAW-1080-1 Check Valve 2

NF 38493-3 2FW - lA 2FW - IB 2FW - 4B Anch 205 905 NF 38493-8 2FW - 5A Loop A 5 B Supports NF 38493-9 2FW - 3A 4A 6A NF 38493-10 2FW - 2A 2B 3B 5B 6B SK-1001 NF 38492-8 FW Restraint NF 39274-1 Physical} 3 FW Restraint Bracket 4 5 6 7 8 9 10 A-3

ATTACHMENT B Std Spec - Hech t FLUOR PIONEER INC. SS - M 368 (NSP) 1-69 Sheet 1 of 2

  • Rev 6-26-72 STANDARD SPECIFICATION FOR PIPING MATERIAL PRESSURE CLASS: Nominal 1500 psi TCIPERATURE LEXIT:  ?!aximum 450'F FEEDWATER PIPING Pipe All piping seamless, ASTM A-106 Grade B, per USAS B36.lv, ends beveled oer PS6C Standard Sketch SK-M474, unless approved otherwi.e by the ENGINEER. Piping schedule and wall thickness as described in Piping Design Table SS - M 327.

Pipe Joints 2" nominal and smaller - Socket velded. 2-1/2" nominal and larger - Butt welded. Welding PS&E Standard Specification :! 400 and M 410. Fittings 2" nominal and smaller - Material ASTM A-131 Grade I or A-105 Grade 2, 3000 lb .WCG per USAS I:16.11. 2-1/2" nominal and larger - Material ASTM A-234 Grade WPBor WPBW, w:d ' thickness B16.9. equal to that of adjoining pipe and conforming to USAS Flanges 2" nominal and smaller - !!aterial ASTM A-105 Grade 2, 900 lb raised face socket weld type per USAS B16.5. Manufceturcr's standard spiral serrated facing. 2-1/2" nominal and larger - Material AStf A-105 Grade 2, 900 lb raised face veld neck type per USAS B16.5. Manufacturer's standard spiral serrated facing. Gaskets Flexitallic Style CG or equal - Contractor shall furnish conplete and accurate flange design data to the gasket manuf acturer to insure that the gasket construction is correct. Bolting Stud-bolt material ASTM A-193 Grade B7 and conforming to USAS B16.5. Nat shall conform to ASDI A-194 Grade 211. Dimensions shall conform with USAS B18.2. 2318 _26 B-1

t FLUOR PIONEER INC. SS - M 368 (NSP) 1-69

  • Sheet 2 of 2
  • Rev 6-26-72 Valves Gate 2-1/2" - 1500 lb per USAS B16.5, body material ASE1 A216 Grade WCB, butt weld ends, pressure seal bonnet, OS&Y, Stellite 6 trim.

3" and larger - 900 lb per USAS B16.5, body material AST'l A216 Grade WCB, butt weld ends, pressure seal bonnet, OS5Y, Stellite 6 trim. Globe-Angle 2" and smaller - 1500 lb per USAS B16.5, body material AST:1 A105 Grade 2, socket weld ends , pressure seal bonnet , OS&Y, Stellite 6 trim. 2-1/2" - 1500 lb per USAS B16.5, body material AST.i A216 Grade WCB, butt weld ends, pressure seal bonnet, OSLY, Stellite 6 trim. 3" and larger - 900 lb per USAS B16.5, body material ASI4 A216 Grade WCB, butt weld ends, pressure seal bonnet, OS&Y, Stellite 6 trim. Check 2" and smaller - 1500 lb per USAS B16.5, piston type, body material AST:1 A105 Grade 2, socket uc1d ends, seal welded bonnet, Stellite 6 trim. 2-1/2" - 1500 lb per USAS B16.5, piston type, body material ASTM A216 Grade WCB, butt weld ends, seal welded or pressure seal bonnet, Stellite 6 trim. 3" and larger - 900 lb per USAS B16.5, balanced disc type , body material AST;! A216 Grade WCB, butt wcld ends, pressure seal bonnet, Stellite 6 trim. 2318 ;27 B-2

P1PlNG D E S I G fi TABLE Rev. 10-15-71 l QA- DESIGH ASTM STD JOINT PIPING SYSTEM FRESS .TEHP SPEC. SPEC. TYPE REHARKS ly TYPE PSIG *F FEEDWATER Tiow Diagrams : NF-39222 (Unit 1) NF-39223 (Unit 2) Piping Drawings v NF-39273-1 6 -2 (Unit 1) $ NF-39274-1 6 -2 (Unit 2) I w m

1. All FU pump disch. piping to first IIA 1500 450 A-106 M-368 m

external restraint up -s tream of Gr. "B" M-400 BW GTAW All piping 8" and larger p to be Sch.100; 6' and' 2 containment penetration, excluding, M-410 smaller to be Sch. EO " recire & warm-up lines n

2. FW piping f rom firs t external re- IA 1500 450 A-106 M-368 BW All piping 8" and larger T straint to first weld out side

" Gr. "B" M-400 GTAW to be Sch. 100; 6" and containment and from first weld M-410 smaller to Sch. 80 except inside containment to steam as noted en pipint drawints generators

3. FW piping from first weld outside IA 2250 450 A-106 M-368 BW 16" Sch. 140 thru containment penetration to Gr. B M-400 GTAW first weld inside M-410 "

m e 3 Le N N 4 u x m m N -4 00

  • Attachment C Index Units 1& 2 Remarks
1. NAVC0 Ltr 6-11-79 Weld prep end pipe-to-pipe
a. SK 18580 Rev. 7 Unit I weld prep of spools
b. SK 20220 Rev. 1 FW-49 and FW-65 Unit 2 weld prep of spools
c. SK 20268 Rev. 2 FW-67 and FW-46
2. NAVC0 Shop Fab Dwgs Spools - 49 6 65 (Unit 1);

with weld histories 67 6 46 (Unit 2); for those spools that Shop welds connect to the steam generators

3. NAVC0 Weld Data Sheets Piping-to-steam generator FW-164 and FW-216 Unit 1 - Field welds
4. NAVC0 Weld Data Sheets Piping-to-steam generator FW-177 and FW-133 Unit 2 - Field welds
5. NAVC0 PWHT Charte For Field welds FW-164, 216, 177 and 133
6. NAVC0 PWHT Applies to both Units for Procedure FE-6 Field welds
7. NAVC0 Welding Procedure Applies to both Units for ITH1-1 rev 1 with PQR Field welds ITH1-I
8. NAVC0 Radiographic Review Documented on envelope; Results for Field welds film and original envelope FW-216, 164, 177 and 133 retained in vault; copy of envelope provided.
9. Additional Field Weld Data These are not all, but are a Sheets FW-156, 213, 208 and representative cross section 161 (Unit 1); FW-170, 169, 131 of pipe-to-pipe / fitting and and 125 (Unit 2) spool-to-valve welds
10. Excerpt from Project Specifi- Applies to both Units as cation Hiawatha #106 SS-M327 principal requirements.

(!!SP) Sheet 6; System Design Tables

11. CMTRs for ASTM A-106 GrC Both Units 1 and 2 material used in Spools (pipe only) FW-65, 49, 67 and 46 2318 329 C-1

PRAIRIE ISLAND UNIT 1 ASYM CLASS ?-Fi<r/4tTsR SY3 TEM Table T TEN YEAR INTERVAL INSPECTION SU'S!ARY Page I of 2 Sub Cocponent or System and Total 40 Yr. 10 Yr. First Interval Item Item to be Inspected Items Amt Amt Act & Period Rcrarks C 2.1 CITUFE3FWTI AL EUT"' WELDS FW-A & 3 MULTIPLE STREAM 3 FEEDWATER A 16-FW-13 17 5 1 1 - PER. TiO 4 ELD F4-lh9, RPr NO. 9c-120 16-FW-12 4 1 1 1 - PER. THREE FEEDUATER B 16-FW-16 16+ 1 - --- 16-FW-15 5 h 1 1 - PER. ONE WELD FW-220, RPT NO. 77-15.9 14 WELDS ARE WELD 3 FW-161, FW-162 FW-164 ENCAPSULATED FW-214, AND FW-216 WERE EXAMINED DURING WEEKEND CUTAG6 ON JUNE 9 & 10, 1979. >

  ~

g 0 2.1 BRANCH PIPE TO PIPE WELD JOIt.S 9 FW-A i 3 MULTIPLE STREAMS S FEEDWATER A 16-FW-1'3 1 1 - --- WELDS FW-16' AND FW-215 We.RS FEEDWATER 3 , EXAMINED DURING WEEKEND CLrTAGE 16-FW-16 1 0 - --- ON JUNE 4 & 10, 1979. 2 2.5 IVTEGRALLY WELDED SUPPORTS FW-A & 3 MULTIPLE STREAMS FEEDWATER A 16-FW-12 1 N/A - --- 16-FW-13 9 N/A 4 2 - P:,3. TW O Q, RPr NO. 79-122,132 2 - PER. THREE N FEEDWATER R u 14-FW-15 1 V/A 1 1 - PER. ONE K. RPr NO. 97-14 16-FU-14 6* 9/A 1 1 - PE3. TWO CD 2 - FER. TMPEE

  • ENCAFSULATED, EXAMINE TO V

FJTENT FO'3SIELE U CD

I PRAIRIE ISLAND U';IT _ASFE CL ASS ?-FEED'4ATER SYSTEM Table I TEN YEAR INTERVAL INSPECTION SDB:ARY Page 2 of 2 Sub Component or System and Total 40 Yr. 10 Yr. First Interval Item Remarks Item to be Inspected Items Amt Amt Amt & Period C 2.6 SUPPORT COvPO?,?O FW-A&B MULTIPLE STREAMS FE3 WATER A 16-FW-1't 0 N/A 0 --- FEEDWATER B 16-FW-16 2* N/A 1 1 - PER. CNE M RPT NO. 77-62

  • ENCAPSULATED 7

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PRAIRIE ISLA';D UNIT 1 FSAR AUr.MENTED - FEED 4ATER SYSTEM 11 Table TEN YEAR INTERVAL INSPECTION SL? DIARY Page 1 of 1 Sub Component or System and Total 40 Yr. 10 Yr. First Interval Item Item to be Inspected Remarks Items Amt Act Act & Period 0 2.1 CIRCUFTERE'?TIAL PUTT WELD 3 FW - A&B F.ULTIPLE STPEAMS FEEDWATER A 16-FW-8 13 N/A 1 1 - PER. TWO WELD FW-124. RP! NO. 78-?,42 2 - PER. THREE FEEDWATER S 16-F'4- 10 "/A ' 1 - PE9 TWO WELD FW-177, RPF NO. 78-44,55 2 - PER. THREE FEEDWATER A FW - A&B F.ULTIPLE STREAE3 16-FW-9 2 N/A - --- Y 16-FW-11 2 N/A 1 1 - PER. T40 WELD FW-128, RPP NO. 76-8,41 16-FW-12 4 N/A 1 1 - PER. ONE WELD FA-147, RPT NO. 77-24,28 FEEDWATER B 16-FW-10 1 N/A 1 1 - PER. THREE 16-FW-14 2 N/A - --- 16-FW-15 5 N/A 1 1 - PER. ONE WELD FW-220, RPI NO. 77-15,9 N U u u N

PRAIRIE ISLAND UNIT ASME CLASS ?-FEEDWATER SYSTSM Table III TEN YEAR INTERVAL INSPECTION

SUMMARY

Page 1 of 2 Sub Component or System and Total 40 Yr. 10 Yr. First Interval Item Item to be Inspected Retarks Ite=s Amt Amt Act & Period 0 2.1 CIRCUMFERENTIAL BUTT WELDS FW - A&B MULTIPLs STREAMS FEEDWATER A 16-2FW-13 15 4 1 1 - PER. ONE WELD FW-161, RPT NO. 77-45,55 16-2FW-12 2 1 - --- 16-2FW-11 2 1 - --- FEED'Jr.TER B 16-2FW-16 16* 1 - --- 16-2FW-14 4 4 1 1 - PER. ONE WELD FW-116, RPT NO. 77-97,3

                                                                   +                   IN ADDITICN, WE ARE PLANNING 15 WELDS ARE ENCAPSULATED        TO ETAMINE THE FEEDWATER PIPS e                                                                                       TO STEAM GENERATOR N0ZZLE
j. WELDS DURING THE NEXT REFUELINO OUTAGE
  >,'   PRANCH PIPE TO PIPE WELD JOINTS                                           FW - A&B MULTIPLE STREAM 3 FEEDWATER A 16-2FW-13                  1      1        -      ---

FEEDWATER B 16-2FW-16 1 0 - --- 125 INTeMRALLY WELDED SUPPORTS FW - A&B MULTIPLE STREAh5 FEEDWATER A 16-2FW-13 9 N/A 5 1 - PER. ONE K, RPT NO. 77-105 16-2PW-12 0 N /A - 2 - PER. TWO ()j 16-2FW-11 1 N/A 1 1- PER. THREE __. FEEDWATER B CX3 16-2FW-16 7* "/A 'l 1 - PER. 0:iE C, RPT NO. 77-104 16-2FW-1< 0 "/A - 1 - PER. TWO 6 1 - PZR. THREE (>4

  • PARTI AL ENCAPSULATION, EXAhlNE le4 TO EXTENT POSSIELE

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nt O ec I t e T sp 2 C ys E S n S P I T.

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PRAIRIE ISLAND UNIT 2 FSA? AU38';TED - FEEDWATER SYSTEM Table IV TEN YEAR INTERVAL INSPECTION SCD'ARY Page 1 of 1 Sub Component or Systec and Total 40 Yr. 10 Yr. First Interval Ites Remarks Item to be Inspected Itens Amt Amt Amt & Period C 2.1 CIMUFERENTI AL PUPr WELD 3 FW - A1B MULTIPLE STREA).S FEEIT.iATER A 16-2FW-8 18 N/A 5 1 - PER ONE WELD FW-151 RPr NO. 77-99,2 1 - PER. TWO UELD FW-148, RPr NO. 78-2,75 3 - PER. THREE FEEWATER P 16-2FW-8 il N/A 3 1 - PER. TWO WELD FW-105, RPr NO. 78-1,76 2 - PER. THPIE FEEDWATER A ? 16-2FW-o 5 N/A 2 1 - PER. ONE WELD FW-152, RPr NO. 77-1,98 16-2FW-11 2 N/A - 1 - ESP. THREE 16-2FW-12 2 N/A - --- FEEDWATER 3 16-2FN-10 h N/A 2 1 - PEP. ONE WELD FN-116, RPr NO. 77-C?,3 16-2FW-15 3 N/A - 1 - PER. THREE N u i.. s U Ln

Attachment E Water Hammer or Vibration History in the Feedwater ,rstem a) Reference letter dated September 2,1975, f rom L 0 Mayer, NSP, to Dennis L Ziemann, Chief Operating Reactors Branch #2. b) Reference letter dated January 29, 1976, from L 0 Mayer, NSP, to Victor Stello, Director, Division of Operating Reactors. c) Reference letter dated December 30, 1977 f rom L 0 Mayer, NSP, to Director of Nuclear Reactor Regulation, U S Nuclear Regulatory Commission. d) On June 8, 1979, while cooling down to perform NDE on Unit I steam generator feedwater nozzles, an abnormal operating condition occurred allowing the steam generator level to decrease below the feedwater ring. It was necessary to lower the steam generator level below the feedwater ring to perform an ef fective NDE on the steam generator nozzle. This was performed before cold shutdown conditions were reached and an apparent secondary system fluid flow instability on Loop B occurred. The condition was corrected by starting the main feed system and introducing warmer feedwater to the steam generator. The feedwater system was inspected for loose hangers, insulation, etc., with no damage noted. The following day, both Loop A and B steam generator nozzleswere inspected as scheduled, utilizing ultra sonic testing and radiography. The results of these examinations were compared with construction tests with no degradation of the system revealed. 2318 336 E-1

Attachment F Feedwater Chemistry - Prairie Island 1 and 2 Prairie Island 1 and 2 are operated using the Westinghouse teedwater specifications listed in Table 7-2 of the " Steam Side Water Chemistry Control Specifications Manual" (SIPS-4) provided by Westinghouse. Unit No. I was placed in commercial operation in December, 1973 using phosphates in the secondary system. The unit was shut down in September, 1974, sludge lanced, inspected, and returned to service on AVT chemistry. Unit No. 2 was started up with AVT chemistry in October of 1974. The feedwater sample taps are located at the inlet to the high pressure heaters and at the final feedwater point just prior to the steam generators. The sample taps are all 19mm connected to a 19mm isolation valve. Immediately af ter the valve the sample line size is reduced to 9.5mm o.d. stainless steel tubing. This tubing continues to the plant's continuous chemistry monitoring instrumentation. Ceeb samples are taken via a parallel sample stream connected upstream of the continuous monitors. The continuously monitored parameters are hydrazine, specific conductivity, and cation conductivity on the feedwater points. Oxygen is continuously monitored at the condensate pump discharge. These process monitors have alarm setpoints and alarm in the chemistry lab and in the control room and plot on a multi-pen recorder in the control room. These process monitors are all calibrated on a set frequency by surveillance test. Grab sample analysis for oxygen, iron, and suspended solids are performed on the feedwater points. All wet analysis procedures are traceable to ASTM or Standard Methods. The feedwater is treated with hydrazine injected at the condensate polisher discharge. The hydrazine pump stroke control manually maintains hydrazine approximately two and one-half times the oxygen level measured at the condensate pump discharge. Ammonium hydroxide is also added at the same location for pH control. The ammonium hydroxide pump stroke control is automatic, sensing specific conductivity in the feedwater, to keep feedwater pH at 9.6. The feedwater chemistry of Prairie Island 1 and 2 has been very consistent. A typical set of values would be: Cation Conductivity 0.11 umhos (with cond polish 0.08) Specific Conductivity 10.0 umhos pH 9.6 0xygen <5 ppb Iron 2 ppb Hydrazine 20 ppb We have maintained a very tight condenser. The plant utilizes fresh water for condenser cooling. Under these conditions chlorides have only rarely been seen in the steam generators which implies the feedwater is maintained with very low chlorides (<.05 ppm). The feedwater at Prairie Island 1 and 2 has been extensively studied under EPRI RP404-1 by Nuclear Water and Waste Technology. Quarterly progress reports #1 through #14 contain a detailed review of secondary system chemistqr parameters.

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