ML20244B818

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Inservice Insp Exam Rept for 881113-890117
ML20244B818
Person / Time
Site: Yankee Rowe
Issue date: 04/10/1989
From:
YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20244B813 List:
References
NUDOCS 8904190434
Download: ML20244B818 (29)
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i INSERVICE INSPECTION EXAMINATION REPORT YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION NOVEMBER 13, 1988 THROUGH JANUARY 17, 1989

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1 8904190434 890410 PDR ADOCK 05000029 o PDC 1

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TABLE OF CONTENTS page-

1. Introduction- 1
2. Evaluation of Data 2 i
3. NIS-1 Owners Data Reports 3
4. Repairs and Modifications 28  ;
5. Conclusions 29' I

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l' . O . INTRODUCTION This report covers the Inservice Inspections'of Yankee Nuclear Power Station from November 13, 1988 to January'1~7, 1989. The inspections performed during this time frame constitute completion of approximately 50% of those examinations required by ASME.Section XI and the Yankee Inservice Inspection Program for the second period of the

-third interval.

The examination methods employed'were Ultrasonics (UT),

Radiography'(RT), Liquid Penetrant (LP), Eddy Current (ET),

Visual Inspection (VT), and Magnetic Particle (MP).

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I fJC: ,.  :. f. O l EVALUATION"OF DATA ]

q The.1988 NDE Inservice Inspections,were performed by.Ebasco

, Services,:Inc., of New York',New York, and Zetec, Inc.,- off Issaquah,'. Washington. 1 c

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All examinations were performed, evaluated ,: and ' reviewedf by' _j personnel certified'to. Level II in accordance with SNT-TC- j 1A, 1975/1980 Edition and ASME.Section XI, 1977 Edition,  ;

Summer 1978 Addenda. 0 The examination methods, volumes, and evaluation of-

$ indications were in accordance.with ASME Boiler and PressureL l

, Vessel Code,Section XI,.1977 Edition, Summer 1978 Addenda,.

except~for Class.1 piping ultrasonic calibration. Class 1 piping calibration was conducted in-accordance'with. Article III-2OOO of. Appendix'III, ASME'Section XI, Summer1976 -

Addenda, as: required per Plant. Technical Specifications.  !

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> The' detailed examination data along with:the calibra?. ion -

3 records,: procedures, personnel and equipment certifications I are maintained at the plant site.

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j FOR4 NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules i

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Yankee Atomic Electric Co., 1671 Worcester Road, Framingham, MA 01701

1. Owner (Name and Address of Owner) ]

. Yankee Nuclear Power Station, Rowe, MA 01367 p

(Name and Address of Plant)

3. Plant Unit Yankee Rowe 4. Owner Certificate of Authorization (if required) DPR-3 7/1/61 Reactor #NB-23964 ]

5, Commercial Service Date 6. National Board Nurnber for Unit

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7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor i

Vessel Babcock Wilcox 610-001 N/A 23964 Steam Generator' Westinghouse N/A N/A 404E(2) l' Piping Stone & Webster N/A N/A N/A Pressurizer Babcock Wilcox 610-0011 N/A 23974E22 O

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Note: Supplemental sheets in form of lists, sketches, or drawings rnay be used provided (1) siec is 8% in. x 11 in., I (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. -l This form (E00029) may be obtained from the Orcier Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 1

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FORM NIS 1 (back)

8. Examination Dates 11/13/88 ,o 1/17/89 9. Inspection Interval from _7[1/81_ to _l/1/SL.
10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. See pages 5-16 l' 1, Abstract of Conditions Noted See pages 17-20
12. Abstract of Corrective Measures Recommended and Taken ,

< See pages 21-27 I

We certify that the statements made in this report are correct and the examinations and corrective mes-sures taken conform to the rules of the ASME Code,Section XI.

N1 Signed X44& r/D 48C NC lh [

Date 8 !83 19 Owner Certifica'te of Authorization No. (if applicable) Expiration Date 7/9/2000 CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspect rs and/or the State or Province of NMrAPSBNF775and employed by >YSA NT d _ of

//ar O 7' have inspected the components described in this Owners' Data Report during the period

//-/'d - 8 to O/ - + 89 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Date /7 hSIN A 19 EV W Commissions Nbl5d] > //) lS ? ?

Inspe,plor's Signature Nationali + rd, State, Province and No. [

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Owner: YANKEE ATOMIC ELECTRIC COMPANYo 580 MAIN STREET, BOLTON, MA 01740 Plant: YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 l Owner Certificate of Plant Units YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964

10. ABSTRACT OF EXAMINATIONS ASME CODE CODE COMPONENTS EXAM -

CATEGORY ITEM NO. EXAMINED METHOD B-B B2.10 50% OF THE UT PRESSURIZER TOP ,

HEAD TO SHELL CIRCUMFERENTIAL WELD (PRTH-C) l B-B B2.11 33-1/3 OF THE UT PRESSURIZER LOWER GHELL IO UPPER SHELL CIRCUMFERENTIAL WELD (PRMH-C)

B-B B2.12 12" OF THE UT PRESSURIZER LONGITUDINAL WELD INTERSECTING THE SHELL CIRCUMFERENTIAL WELD (PRTH-L-A)

B-B B2.12 12" OF THE UT.

PRESSURIZER LONGITUDINAL WELD INTERSECTING THE TOP HEAD (PRTH-L-B)

B-B B2.60 100% OF '- LP FEED /BLEdu HEAT EXCHANGER TUBE SHEET TO BOTTOM HEAD WELD (FBB-1-2)

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, ,' Owners YANKEE-ATOMIC-ELECTRIC-COMPANY, 5BO MAIN STHEET, BOLTON, MA 01740 Plant: YANKEF NUCLEAR POWER STATION, ROWE, MA 01367 1 Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 i

Commercial National Board Service Date 7/1/61 Number-for Unii: REACTOR #NB-23964 l

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10. ABSTRACT OF EXAMINATIONS- 1 1

ASME CODEL CODE COMPONENTS. EXAM. J CATEGORY JTEM NO. EXAMINED METHOD: l B-D B3.110 PRESSURIZER UT NOZZLE TO VESSEL 1 WELD I (PRZN-10)

B-E B4.20 PRESSURIZER VT-2 NOZZLE PARTIAL PENETRATION WELD (PRZN-3)

B-F- B5.20 PRESSURIZER LP/RT  !

NOZZLE TO SAFE END WELD (PRZ-SE-10) ,

B-F B5.30 (2) STEAM LP/UT/RT  ;

GENERATOR NOZZLE TO SAFE END WELDS (MC-3-6, MC-3-9)

B-G-1 B6.60 PRESSURIZER VT/UT MANWAY STUDS & l NUTS - IN PLACE  !

B-G-2 B7.20 PRESSURIZER VT .:

HEATER BOLTS - IN PLACE i (PR-HP-2)

B-G-2 B7.30 #3 STEAM VT GENERATOR PRIMARY I MANWAY STUDS & q NUTS l 1

! B-G-2 B7.60 #1 AND #4 MAIN MP/VT ,

COOLANT PUMP STATOR CAP BOLTS

Owners YANKEE ATOMIC ELECTRIC COMPANY, 580 MAIN STREET, BOLTON, MA' 01740'

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Plants. YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Unit: YANKEE ROWE Authorization.(if required): 'DPR-3 Commercial National Board Service Date 7/1/61 Number for Unit: REACTOR #NB-23964 I

10. ABSTRACT OF EXAMINATIONS' -

ASME CODE CODE COMPONENTS EXAM CATEGORY. ITEM NO. EXAMINED METHOD

-B-G-2 97.60 #2 AND #3 MAIN VT COOLANT PUMP i STATOR CAP BOLTS-B-G-2 B7.70 BOLTING (8) VT VALVES (MC-V-301, MC-V-302, MC-MOV-502, MC-V-308, MC-V.322, MC-MOV-325,.

PR-SV-181, PR-SV-182)

B-H BS.20 PRESSURIZER MT INTEGRALLY WELDED SUPPORT (PRS-H-4A)

B-J- 89.11 (10) RT/UT CIRCUMFERENTIAL MP OR LP PIPE WELDS 4" AND GREATER (MC-3-11, MC-3-14, MC-3-8, MC-3-7, PRS-1, SDC-12, SI-2-14, SI-2-9, ,

SI-3-9, l SI-3-10)

B-J B9.30 (1) BRANCH PIPE UT/LP CONNECTION WELD (SI-2-BR-1)

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Owners YANKEE ATOMIC ELECTRIC COMPANY,J580 MAIN STREET, BOLTON, MA 01740 Plant: YANKEE NUCLEAR-POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Unit: YANKEE ROWE' Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit -REACTOR #NB-23964

10. ABSTRACT OF EXAMINATIONS ASME CODE CODE COMPONENTS EXAM CATEGORY ITEM NO. EXAMINED METHOD B-J B9.40 (9)-SOCKET ' WELDS ILP 2" AND LESS (BL-1-29, BL-1-29, CH-55, CH-58, DRH-20, DRH-22, DRH-25, PR-206-17, PRS-206-20)

B-K-1 B10.20 (4) INTEGRALLY LP WELDED PUMP i SUPPORTS j (CRM-H-13, CRM-H-14, CRM-H-27, CRM-H-28)

B-K-2" B11.10 (15) PIPING VT-3/VT-4 COMPONENT ,

SUPPORTS l sCH-F-2, CRBH-RH-4, CRB-H-29,  !

CRCH-R-4, DRH-H-5, DRH-H-8, -

H-3, CRM-H-4, CRM-H-3, .

PRCH-H-4, 1 PRCH-SNB-1A, PRSH-RH-22, PRSH-SNB-1, PRSH-SNB-5, PRSH-SNB-9)

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, Owners! YANKEE ATOMIC ELECTRIC COMPANY, 580 MAIN STREET, BOLTON, MA 01740 Plant: YANKEE NUCLEAR POWER. STATION, ROWE, MA 01367.

Owner Certificate of Plant Unit:- YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964

10. ABSTRACT OF' EXAMINATIONS ASME CODE CODE COMPONENTS- EXAM CATEGORY ITEM NO. EXAMINED METHOD B-M-2 'B12.4C (3) VALVE' BODIES VT-3 GREATER THAN 4" INTERNAL SURFACES-(MC-MOV-325, MC-MOV-301, MC-V-322)

B-P B15.20- MAIN COOLANT VT-2 B15.71 SYSTEM LEAKAGE TEST B-O B16.20 100% GF THE #3 ET STEAM-GENERATOR TUBES PER YANKEE TECHNICAL SPECIFICATIONS L

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Owners- YANKEE ATOMIC [ ELECTRIC COMPANY, 500 MAIN STREET, BOLTON, MH 01740 Plants YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964

10. ABSTRACT OF EXAMINATIONS ASME CODE CODE COMPONENTS EXAM CATEGORY ITEM NO. EXAMINED METHOD LC-A C1.10 50% OF THE #4 STEAM GENERATOR SHELL CIRCUMFERENTIAL WELD (SG-4-4)

'C-A C1.20 33-1/3% OF THE #3- UT STEAM GENERATOR-HEAD TO SHELL WELD.

(SG-3-6)

C-A C1.30 40% OF THE STEAM UT GENERATOR TUBE SHEET TO SHELL WELD (DISTRIBUTED BETWEEN SG-3-2 AND SG-4-2)

C-B- C2.10 (1) SAFETY MT INJECTION ACCUMULATED NOZZLE WELD (SI-ACC-NZ-1)

C-B C2.20 (4) STEAM UT/MT GENERATOR NOZZLE WELDS (SG-1-FN),

SG-1-SO, SG-2-SO, SG-4-S0)

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. . .. Ownera'- VANKEE ATOMIC'ELECTR'IC.COMPANYo 580 MAIN STREET, BOLTON, MA 01740 i

" Plant: YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 ll Owner Certificate of Plant Unit: YANKEE ROWE -Authorization (if required): DPR-3 Commercial National' Board Number for Units. REACTOR #NB-23964-

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' Service Date: 7/1/61

10. ABSTRACT OF EXAMINATIONS ASME CODE CODE COMPONENTS EXAM CAllsGORY ITEM NO. EXAMINED METHOD CC-CE C3.10 (1) SAFETY MT INJECTION ACCUMULATOR INTEGRALLY WELDED SUPPORT (SI-ACC-S-1)

CC-CE C3.20 (5) STEAM VT GENERATOR COMPONENT SUPPORTS (SG-2-S-E, SG-2-S-N, SG-2-S-S, SG-2-S-W, SG-4-S-E)

CC-CE C3.30 (1) STEAM VT GENERATOR SNUBBER (SG-2-441-SN)

CC-CE C3.50 (17) PIPING VT COMPONENT SUPPORTS (SHP-H-4, WCBD-H-131-4, WCBD-H-134-4, WCBD-RH-123, WCBD-RH-118A, WCBD-RH-121-C, WCBD-RH-124-4, BRL-H-53, H-11A, l

H-31, H-33, HPSI-RH-9, l PRCL-H-41, l CRT-il-62, PRCL-S-51, WCBD-RH-123A, WCBD-124-1) m_______._____________ _ _ _ _ _ _ _ _ _ _ _ _ . i

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,. . Owners YANKEE ATOMIC ELECTRIC COMPANY, 580 MAIN STREET,

_ BOLTON, MA 01740 Plant: YANKEE NUCLEAR' POWER STATION, ROWE, MA 01367-Owner Certificate ofL Plexit Units' YANKEE.ROWE Authorization (if required):- DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964

10. ABSTRACT OF EXAMINATIONS ASME CODE CODE- ' COMPONENTS EXAM  !

' CATEGORY ITEM NO. EXAMINED METHOD C-F C5.11 (18) LP OR MP CIRCUMFERENTIAL' PIPING WELDS (PRS-2-23,

.SDC-1-12, SDC-1-9, SDC-3-12, SDC-3-19, SDC-3-21, SDC-3-6, SDC-3-9, SI-011, SI-014, SI-017, SI-029, SI-032, SI-038, SI-11A, 94 -14C ,

FW 21, FW 26 )

C-F C5.21 (9) UT/MT CIRCUMFERENTIAL PIPING WELDS (MS-2-22, MS-4-15,

.MS-2-6, MS-2-7, MS-2-11, MS-2-12, MS-1-1, MS-2-2, 94-1C)

,. Dwners LYANKEE ATOMIC. ELECTRIC' COMPANY,-580 MAIN STREET, I BOLTON, MA 01740 Plant: ' YANKEE. NUCLEAR' POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Unit. YANKEE ROWE. Authorization (if' required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit -REACTOR #NB-23964

10. ABSTRACT OF EXAMINATIONS

'ASME CODE CODE COMPONENTS EXAM CATEGORY ITEM NO. EXAMINED METHOD C-H C7.10- CHARGING. PUMP VT-2 SYSTEM C7.40 SUCTION HEADER HYDROSTATIC TESTS HIGH PRESSURE SAFETY INJECTION i

LOW PRESSURE SURGE TANK COOLING CHARGING PUMP SUCTION PIPING SHUTDOWN COOLING SYSTEM i

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i Owners YANKEE 1 ATOMIC ELECTRIC COMPANY,'580 MAIN STREET, 1 BOLTON,-MA 01740 Plant: ANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Unit: . YANKEE ROWE Authorization (if required): DPR-3

' Commercial National Board' Service Date: 7/1/61 Number for Units REACTOR #NB-23964

10. ABSTRACT OF EXAMINATIONS
ASME CODE CODE COMPONENTS EXAM

' ITEM NO. EXAMINED METHOD CATEGORY i

.D-A D'.1.1.(a) CLASS 3 COMPONENT VT-2 COOLING SYSTEM INSERVICE' TEST .

CLASS 3 PRIMARY PUMP SEAL WATER CLASS 3 SERVICE WATER D-A D.1.1.(b) VENT PIPING TO VT-2 WD-V-980 AND 837A HYDROSTATIC-TEST-I

Owners- . YANKEE ATOMIC ELECTRIC COMPANY,-580 MAIN STREET, BOLTON, MA 01740 Plants YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 I

~ Owner Certi ficate of

. Plant Unit: YANKEE ROWE ' Authorization (if-required): DPR-3 1

Commercia! National Board-

? Service.Date: 7/1/61 Number for Unit REACTOR #NB-23964

10. ABSTRACT OF EXAMINATIONS ASME' CODE CODE ' COMPONENTS EXAM CATEGORY ITEM NO'. EXAMINED- METHOD' D-A D.1.2 (28) COMPONENT' VT-3

' COOLING SYSTEM HANGERS' (K-S-51,.

K-H-50, K-H-51, K-H-52, K-H-53',

K-H-54, K-H-55, K-H-56, K-H-57 , -

K-H-58, K-H-66, K-H-72, K-H-73, K-H-74, K-H-76, K-R-1, K-S-50, K-S-52, K-S-53, K-S-54, K-S-55, K-S-56, K-S-59, K-S-60, '

K-S-64, K-S-66)'

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., Owners. .. YANKEE' ATOMIC: ELECTRIC COMPANY, 580 MAIN S'REET, BOLTON, MA LO1740 Plant YANKEE-NUCLEAR POWER l STATION, ROWE,: MA 01367 Owner Curti+icate af.

Plant Unit YANKEE ROWE ' Authorization (if required): .DPR-3

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Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964 3

10. ABSTRACT OF EXAMINATIONS' ASME CODE CODE COMPONENTS EXAM CATEGORY ITEM NO. EXAMINED METHOD D-A D.1.2 (17) SERVICE; VT-3 WATER SYSTEM HANGERS (WS-A-2, WS-A-3, WS-H-24, WS-H-72, WS-H-73, WSL-H-10, WSL-H-11, WSL-H-12, WSL-H-13, WSL-H-14, WSL-H-15, WSL-S-2,.

WS-S-10, WSL-H-6, WSL-H-7, WSL-H-8, WSL-H-9).

D-C- D.3.1(b) SPENT FUEL PIT VT-2 SYSTEM  !

COOLING SYSTEM HYDROSTATIC TEST l

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, ' :,. ' DwneN s ; ' YANKEE' ATOMIC' ELECTRIC COMPANY,.580 MAIN STREET,.

BOLTON, MA 01740 Plants; YANKEE' NUCLEAR POWER STATION, ROWE, MA '01367 '

Owner Certificate-of Plant Unit YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964-

11. - ABSTRACT OF CONDITIONS NOTED.

ASME CODE CODE CATEGORY ITEM NO. CONDITIONS'NOTED B-G-2 B7.30 VISUAL EXAMINATION OF THE tK5 STEAM GENERATOR PRIMARY MANWAY REVEALED (7)1 STUDS WITH MINOR MECHANICAL TM3EAD DAMAGE.

(NC-7, NC-54, NC-26, NC-82, NC-15, NC-69, NC-96)

B-G-2 87.60 VISUAL' EXAMINATION OF THE #4 MAIN COOLANT PUMP' STATOR CAP BOLTS-REVEALED (12) BOLTS WITH MINOR CORROSION DAMAGE AND (2) BOLTS WITH AXIAL LINEAR INDICATIONS ON THE BOLT HEAD.

B-J B9.11 ULTRASONIC EXAMINATION OF WELD SDC-12 REVEALED SEVERAL RECORDABLE INDICATIONS.

B-J B9.11 ULTRASONIC EXAMINATION OF WELD SI-2-9 REVEALED A RECORDABLE INDICATION.

B-C B9.11 ULTRASONIC EXAMINATION OF WELD SI-3-9 REVEALED A RECORDABLE INDICATION.

B-K-2 B11.10 VISUAL EXAMINATION OF CHARGING SYSTEM PIPE HANGER CRCH-R-4 REVEALED A LOOSE CLAMP.

B-O B16.20 EDDY CURRENT EXAMINATION OF THE #3 STEAM GENERATOR TUBES REVEALED (8)

TUBES WITH WALL DEGRADATION OF 38-64%.

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,; Owners -YANKEE ATOMIC' ELECTRIC COMPANY, 590 MAIN STREET, BOLTON,_ MA 01740 Plant: YANKEE NUCLEAR POWER' STATION,.ROWE,: MA. 01367

' Owner Certificate of Plant Unit YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Dates :7/1/61 Number for Unit: REACTOR #NB-23964

.1 1. ABSTRACT OF CONDITIONS NOTED

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ASME CODE CODE-CATEGORY II'EM NO. CONDITIONS NOTED' C-A C1.10 ULTRASONIC EXAMINATION OF #4 STEAM GENERATOR SHELL' WELD (SG-4-4)

REVEALED SEVERAL RECORDABLE INDICATIONS.

.C-A C1.20 ULTRASONIC EXAMINATION OF #3. STEAM GENERATOR TUBE SHEET TO SHELL WELD (SG-3-2) REVEALED.SEVERAL RECORDABLE INDICATIONS.

C-B C2.20 ULIRASONIC EXAMINATION OF'#1 STEAM GENERATOR FEEDWATER NOZZLE WELD (SG-1-FN)-REVEALED.SEVERAL RECORDABLE I ND I C AT I ONS . -

C-B C2.20 MAGNETIC' PARTICLE AND ULTRASONIC EXAMINATION OF #1 STEAM GENERATOR STEAM OUTLET NOZZLE WELD '

(SG-1-S0) REVEALED.SEVERAL UNACCEPTABLE MAGNETIC PARTICLE' INDICATIONS AND-SEVERAL RECORDABLE ULTRASONIC INDICATIONS.

C-D' C2.20 ULTRASONIC EXAMINATION OF #2 STEAM GENERATOR OUTLET NOZZLE WELD (SG-2-SO) REVEALED SEVERAL RECORDABLE INDICATIONS.

C-B C2.20 ULTRASONIC EXAMINATION OF #4 STEAM GENERATOR STEAM OUTLET NOZZLE REVEALED SEVERAL RECORDABLE INDICATIONS.

'DC-CE C3.50 VISUAL EXAMINATION OF FEEDWATER HANGER WCBD-RH-123-B REVEALED A WORN TURNBUCKLE BOLT.

CC-CE C3.50 VISUAL EXAMINATION OF FEEDWATER HANGER WCBD-RH-124-4 REVEALED A LOOSE' NUT.

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. Owner 8f YANKEE. ATOMIC ELECTRIC COMPANY, 580 MAIN STREET,

'BOLTON, MA 01740 l

Plant: YANKEE. NUCLEAR POWER STATION, ROWE, MA .01367' 1

Owner Certificate of Plant Unit: 'ANKEE ROWE Authorization (if required): :DPR-3 Commercial National Board.

Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964 I

11. ABSTRACT:OF CONDITIONS NOTED

_ASME CODE CODE CATEGORY ITEM NO. CONDITIONS-NOTED CC-CE C3.50 VISUAL EXAMINATION OF PRESSURE CONTROL AND RELIEF PIPING HANGER BRL-H-53 REVEALED A LOOSE NUT.

CC-CE C3.50- VISUAL EXAMINATION OF SHUTDOWN COOLING. PIPING SUPPORT PRCL-S-51 REVEALED A LOOSE BOLT.

C-F C5.21 ULTRASONIC EXAMINATION OF MAIN STEAM LINE WELD MS-2-22 REVEALED SEVERAL RECORDABLE INDICATIONS.

C-F C5.11 MAGNETIC PARTICLE EXAMINATION OF FEEDWATER PIPING WELD FW-4 REVEALED A LINEAR' INDICATION.

C-F C5.21 ULTRASONIC EXAMINATION OF MAIN STEAM LINE WELD MS-4-15 REVEALED SEVERAL RECORDABLE INDICATIONS.

.C-F C5.21 ULTRASONIC EXAMINATION OF MAIN STEAM LINE WELDS MS-2-6, MS-2-7, MS-2-11, MS-2-12, MS-1-1 AND MS-1-2 ALL REVEALED RECORDABLE INDICATIONS.

C-H C7.10- VISUAL EXAMINATION OF PORTIONS OF C7.40 THE CHARGING PUMP SUCTION HEADER REVEALED SEVERAL MINOR FLANGE LEAKS l (OP-2OOO.201)

C-H C7.10- VISUAL EXAMINATION OF THE CHARGING C7.40 PUMP SUCTION PIPING IDENTIFIED A MINOR PACKING LEAK (OP-2OOO.199)

C-H C7.10- VISUAL EXAMINATION OF PORTIONS OF

C7.40 THE SHUTDOWN COOLING SYSTEM l IDENTIFIED A MINOR VALVE BODY TO BONNE T LEAK (OP-2OOO.196)

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Own'er YANKEELATOMIC ELECTRIC COMPANY,.580 MAIN' STREET,

'BOLTON,'MA 01740 PIant: YANKEE NUCLEAR POWER STATION, ROWE, MA 01367-Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 Commercial . National Board l Service Dates- 7/1/61 Number for Units REACTOR #NB-23964 11'. ABSTRACT OF CONDITIONS NOTED ASME CODE' CODE CATEGORY ITEM NO. CONDITIONS NOTED D-A D.1.2 VISUAL EXAMINATION OF COMPONENT COOLING SUPPORT K-H-56 REVEALED ,

GALLING OF A' THREADED ROD AND MINOR MECHANICAL DAMAGE TO A SUPPORT MEMBER.

D-A D.1.2 VISUAL EXAMINATION OF. COMPONENT COOLING SUPPORT K-S-2 REVEALED CORROSION OF SUPPORT MEMBERS.

D-A D.1.2 VISUAL EXAMINATION OF COMPONENT COOLING SUPPORT K-S-64 REVEALED CORROSION OF SUPPORT MEMBERS.

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.c Ownsrs 'YANKEELATOMIC-ELECTRIC COMPANY,'580 MAIN STREET, BOLTON, MA 01740 Plant: YANKEE. NUCLEAR POWER STATION, ROWE, MA- 01367 l Owner Certificate of l Plant Units YANKEE ROWE Authorization.(if required): DPR-3 Commercial National Board  ;

Service Dates 7/1/61 Number for Unit REACTOR #NB-23964

12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN ASME-CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN B-G-2 B7.30 THE MINOR MECHANICAL DAMAGE (GALLED THREADS).ON (7) STEAM GENERATOR  !

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PRIMARY ~MANWAY STUDS WERE REPAIRED BY CHASING THE THREADS. THE STUDS.  ;

WERE REINSPECTED SATISFACTORY AND I RETURNED TO SERVICE.

~ B-G-2 B7.60 (9) OF THE (16) #4 MAIN COOLANT I PUMP STATOR CAP BOLTS WITH MINOR I CORROSION AND AXIAL INDICATIONS  !

WERE REPLACED IN KIND. THE REMAINING (7) BOLTS WERE SUBJECTED TO A MAGNETIC PARTICLE EXAMINATION.

THE BOLTING WAS SUBSEQUENTLY-  :

DETERMINED TO BE ACCEPTABLE FOR )

CONTINUED SERVICE.

AS REQUIRED BY IWB-2430 AN ADDITIONAL EXAMINATION WAS SELECTED. .THE STATOR CAP BOLTING-ON #1 MAIN COOLANT PUMP WAS SUBJECTED TO A VISUAL AND MAGNETIC PARTICLE EXAMINATION WITH NO '

UNACCEPTABLE CONDITIONS NOTED. IN ADDITION THE BOLTING ON #2 AND #3 MAIN COOLANT PUMPS WERE VISUALLY l INSPECTED WITH NO UNACCEPTABLE CONDITIONS NOTED.

B-J B9.11 THE ULTRASONIC REFLECTORS RECORDED IN SHUTDOWN COOLING WELD SDC-12, SI-2-9 AND SI-3-9 WERE SUBSEQUENTLY EVALUATED IN ACCORDANCE WITH IWB-3514.5 AND DETERMINED TO BE GEOMETRIC REFLECTORS.

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Owners l YANKEE ATOMIC ELECTRIC' COMPANY, 5G0 MAIN STREET,

-BOLTON, MA 01740 Plant: ' YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Unit: YANKEE.ROWE Authorization-(if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964

12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED'AND TAKEN ASME CODE CODE CATEGORY' ITEM NO. CORRECTIVE' MEASURES TAKEN B-K-2 B11.10 THE LOOSE CLAMP IDENTIFIED ON CHARGING HANGER CRCH-R-4 WAS SUBSEQUENTLY TIGHTENED. THE CONDITION WAS DETERMINED TO BE NON-SERVICE INDUCED.

B-Q B16.20 THE.(8) . TUBES IN #3 STEAM GENERATOR EXHIBITING WALL LOSSES OF GREATER THAN 35%.WERE PLUGGED BY MECHANICAL MEANS. A COMPLETE REPORT OF THE

.1988 STEAM G7NERATOR' EDDY CURRENT EXAMINATION ACTIVITIES WILL BE FILED IN ACCORDANCE WITH PLANT TECHNICAL SPECIFICATIONS..

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, Owners , YANKEE ATOMIC ELECTRIC COMPANYo 580 MAIN STREETo-BOLTON,'MA 01740 ,

Plant: YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Owner Certificate of-

' Plant Unit: YANKEE ROWE Authorization-(if required): DPR-3 Commercial National Board Service Date: 7/1/61- Number for' Unit: REACTOR #NB-23964

12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN

'ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN C-A C1.10 THE ULTRASONIC INDICATIONS RECORDED ON #4 STEAM GENERATOR SHELL WELD (SG-4-4) WERE SUBSEQUENTLY.

EVALUATED IN ACCORDANCE WITH l IWP-3514.5 AND DETERMINED TO BE  !

GEOMETRIC REFLECTIONS.

C-A 'C1.20 THE ULTRASONIC REFLECTORS IDENTIFIED ON #3 STEAM GENERATOR TUBE SHEET TO SHELL WELD (SG-3-2)

WERE SUBSEQUENTLY EVALUATED AND DETERMINED TO BE WITHIN THE ACCEPTANCE LIMITS OF ASME SECTION XI IWB-3OOO.

C-B C2.20 THE ULTRASONIC REFLECTORS NOTED IN THE #1 STEAM GENERATOR FEEDWATER NOZZLE TO VESSEL WELD (SG-1-FN)

WERE SUBSEQUENTLY EVALUATED AND DETERMINED TO BE FABRICATION RELATED. THE NOZZLE WILL BE RE-EXAMINED DURING THE NEXT REFUELING OUTAGE TO VERIFY NO CHANGE IS' OCCURRING.

C-B C2.20 THE UNACCEPTABLE MAGNETIC PARTICLE INDICATIONS ON #1 GTEAM GENERATOR OUTLET NOZZLE (SG-1-S0) WERE REMOVED BY LIGHT BUFFING AND THE AREAS WERE RE-EXAMINED SATISFACTORY. IN ACCORDANCE WITH IWC-2340 AN ADDITIONAL OUTLET NOZZLE WAS SELECTED FOR EXAMINATION (SG-2-S0). THIS EXAMINATION DID NOT REVEAL ANY UNACCEPTABLE CONDITIONS.

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.' Owners; VANKEE ATOMIC ELECTRIC COMPANY, 580 MAIN STREET, BOLTON, MA 01740 Plants. YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Dwner Certificate of Plant Units. YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964

12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN i

C-D C2.20 THE ULTRACONIC REFLECTORS NOTED.IN

  1. 1, 2 AND 4 STEAM GENERATOR OUTLET NOZZLES (SG-1-SO, SG-2-SO, SG-4-SO)

WERE SUBSEQUENTLY EVALUATED AND-DETERMINED.TO BE FABRICATION RELATED AND ACCEPTABLE FOR CONTINUED SERVICE.

CC-CE' C3.50 THE WORN TURNBUCKLE BOLT'NOTED ON FEEDWATER HANGER WCBD-RH-123B WAS REPLACED IN KIND. IN ACCORDANCE WITH IWC-2430 AN ADDITIONAL HANGER WAS SELECTED FOR EXAMINATION

( WCBD-Ril-123A ) . THE EXAMINATION DID NOT REVEAL ANY UNACCEPTABLE CONDITIONS.

CC-CE .3.50 THE LOOSE NUT NOTED ON FEEDWATER HANGER WCBD-RH-124-4 WAS TIGHTENED.

IN ACCORDANCE WITH IWC-2430 AN ADDITIONAL HANGER WAS SELECTED FOR EXAMINATION (WCBD-RH-124A). THIS EXAMINATION DID NOT IDENTIFY ANY SIMILAR UNACCEPTABLE CONDITIONS.

l CC-CE C3.50 THE LOOSE NUT ON PRESSURE CONTROL AND RELIEF PIPING HANGER BRL-H-53 WAS TIGHTENED. IN ACCORDANCE WITH IWC-2340 AN ADDITIONAL HANGER WAS l SELECTED FOR EXAMINATION l (BRL-H-52). THIS EXAMINATION DID NOT IDENTIFY ANY SIMILAR UNACCEPTABLE CONDITIONS.

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Owner: YANKEE ATOMIC ELECTRIC COMPANY, 580 MAIN STREET,

-. '- -BOLTON,'MA 01740

, ~ Pl an t's YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Units YANKEE ROWE Authorization (if required): DPR-3 Commercial- National Board' Service Date: 7/1/61 Number for Unit REACTOR #NB-23964

12. ABSTRACT'OF CORRECTIVE MEASURES RECOMMENDED AND'TAKEN ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES'TAKEN l CC-CE C3.50 THE LOOSE BOLT 10N SHUTDOWN COOLING PIPING SUPPORT PRCL-S-51 WAS' TIGHTENED. IN ACCORDANCE WITH IWC-2430 AN ADDITIONAL SUPPORT WAS SELECTED FOR EXAMINATION (PRCL-H-60). THIS EXAMINATION DID NOT IDENTIFY ANY SIMILAR UNACCEPTABLE CONDITIONS.

C-F C5.11 THE MAGNETIC PARTICLE INDICATION ON FEEDWATER PIPING WELD FW-4-26 WAS u SUBSEQUENTLY EVALUATED TO BE FABRICATION RELATED AND' DETERMINED-ACCEPTABLE FOR CONTINUED SERVICE.

C-F C5.21 THE ULTRASONIC REFLECTORS NOTED IN MAIN STEAM LINE WELDS MS-2-22, MS-4-15, MS-2-6, MS-2-7, MS-2-11 AND MS-2-12 WERE ALL SUBSEQUENTLY EVALUATED IN ACCORDANCE WITH IWB-3514.5 AND DETERMINED TO BE GEOMETRIC REFLECTIONS.

C-H C7.10- THE FLANGE LEAKS NOTED DURING THE C7.40 CHARGING PUMP SUCTION HEADER HYDROSTATIC TEST WERE SUBSEQUENTLY CORRECTED BY REPLHOING THE GASKETS.

A VISUAL RE-EXAMIN/4 TION VERIFIED l THE LEAKAGE WAS CORRECTED.

C-H C7.10- THE PACKING LEAK IDENTIFIED DURING C7.40 THE CHARGING PUMP SUCTION PIPING HYDROSTATIC TEST WAS CORRECTED BY ADJUSTING THE PACKING. A VISUAL RE-EXAMINATION VERIFIED THE LEAKAGE WAS CORRECTED.

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c . . . Owner YANKEE' ATOMIC ELECTRIC-COMPANY,.580 MAIN STREET, BOLTON, MA 01740 Plant: YANKEE. NUCLEAR. POWER STATION, ROWE,-MA 01367 Owner Certificate of Plant Unit YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date 7/1/61 Number for' Units REACTOR MND-23964
12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN C-H C7.10- A MAINTENANCE REQUEST WAS ISSUED-

.C7.40 FOR REPAIR.0F THE DODY TO BONNET LEAK NOTED ON A' SHUTDOWN COOLING SYSTEM VALVES (CH-V-661)

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... Owners VANKEE ATOMIC ELECTRIC COMPANY, 580 MAIN STREET, BOLTON, MA -01740

_ Plant: YANKEE NUCLEAR POWER STATION, ROWE, MA 01367 Owner Certificate of Plant Units YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964~

.12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN i

D-A' D.1.2 THE THREADED ROD WITH MINOR  ;

MECHANICAL DAMAGE ON COMPONENT COOLING SUPPORT K-H-56 WAS REPLACED IN KIND. THE CONDITION WAS DETERMINED TO BE NON-SERVICE INDUCED.

D-A D.1.2 A MAINTENANCE REQUEST WAS GENERATED FOR THE REPAIR OF CORRODED COMPONENT COOLING SUPPORT K-S-52.

AS REQUIRED BY IWC-2430 AN ADDITIONAL SUPPORT WAS SELECTED FOR p EXAMINATION (K-S-57). THIS EXAMINATION DID NOT REVEAL ANY SIMILAR UNACCEPTABLE CONDITIONS.

D-A D.1.2 A MAINTENANCE REQUEST WAS GENERATED FOR REPAIR OF CORRODED COMPONENT COOLING SUPPORT K-S-64. AS REQUIRED BY'IWC-2430 AN ADDITIONAL SUPPORT WAS SELECTED FOR EXAMINATION (K-S-69). THIS EXAMINATION DID NOT REVEAL ANY SIMILAR UNACCEPTABLE CONDITIONS.

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REPAIRS AND REPLACEMENTS The following ASME Section XI repairs / replacements were performed during the time frame of July 3, 1987 to January 17, 1989:

Maintenance Request 87-1062 Replacement of HC-V-828 - Heating Steam to EBFP Isolation Valve Maintenance Request 87-1857 Replacement of AS-V-757 - Aux Steam j Supply to EBFP Isolation Valve l Maintenance Request 88-1520 Repair Body to Bonnet Seating.

Surface of BF-FCV-13OOA Maintenance Request 88-1660 Repair of a Linear Indication on H the Safety Injection Tank Weld Maintenance Request 88-2042 Installation of Spool' Piece on Steam Generator Blowdown Line Plant Design Change 86-011 Safety Injection Tank Recirc Pump Replacement Safe Shutoown System Piping  !

Engineering Design Change 86-302 Modifications l Plant Design Change 87-017 Installation of Cross Bracing on Component Cooling Water Storage Tank Engineering Design Replacement of SW-TV-408 Change 88-306 Engineering Design Installation of Tie-in Connections Change 88-3)O for Water Cleanup System l

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,, G.O CONCLUSIONS The examinations completed and identified within this report constitute completion of approximately 50% of those examinations required by the Yankee Nuclear Power Station Technical Specifications for the second period of the third interval.

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