BSEP 03-0137, Inservice Inspection Program for the Third 10-Year Interval-Refueling Outage 15 (B216R1) Owner'S Activity Report

Inservice Inspection Program for the Third 10-Year Interval-Refueling Outage 15 (B216R1) Owner'S Activity Report

ML033010513
Person / Time
Site:	Brunswick
Issue date:	10/20/2003
From:	O'Neil E Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 03-0137
Download: ML033010513 (17)

Text

Progress Energy OCT 2 0 2003 SERIAL: BSEP 03-0137 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/LICENSE NO. DPR-62 INSERVICE INSPECTION PROGRAM FOR THE THIRD 10-YEAR INTERVAL-REFUELING OUTAGE 15 (B216R1) OWNER'S ACTIVITY REPORT Ladies and Gentlemen:

This letter submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-1 Owner's Activity Report for Progress Energy Carolinas, Inc.'s (PEC)

Brunswick Steam Electric Plant (BSEP), Unit No. 2. The enclosed Form OAR-1 Owner's Activity Report covers the period from May 30, 2001, through August 26, 2003.

ASME Code Case N-532-1, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1," requires an Owner's Activity Report Form OAR-1 to be prepared and certified upon completion of each refueling outage. On August 7, 2003, a revision to 10 CFR 50.55a went into effect which incorporates by reference NRC Regulatory Guide 1.147, Revision 13, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1." This revision of Regulatory Guide 1.147 conditionally accepts the use of ASME Code Case N-532-1. As specified by the ASME Code Case, the Form OAR-1 Owner's Activity Report for BSEP, Unit 2 Refueling Outage 15 (i.e., B216R1) is provided in Enclosure 1.

Table 2 of the Form OAR-1 Owner's Activity Report lists flaws or relevant conditions that required evaluations for continued service. The table list only one condition, which involves the bolted connection at valve B32-FO31B, "Recirc Loop B Discharge Valve,"

which required evaluation. Subparagraph IWB-3144(b) of the ASME Code,Section XI, requires that evaluation analyses of examination results for the affected components be submitted to the regulatory authority having jurisdiction at the plant site. Accordingly, provides a copy of the evaluation of the examination results for leakage at the bolted connection for valve B32-F031B, identified during Unit 2 Refueling Outage 15.

Progress Energy Carolinas. Inc.

Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461

Document Control Desk BSEP 03-0137 / Page 2 Table 3 of the Form OAR-1 Owner's Activity Report lists one repair and one replacement activity previously involving the NRC. The repair of a through-wall leak on line 2-SW-103-24-157 was previously authorized by the NRC in a letter dated March 15, 2002, and documentation of this repair was provided by PEC's letter dated May 12, 2003 (Serial:

BSEP 03-0069). The replacement activity involved a relief request submitted by PEC's letter dated October 25, 2002 (Serial: BSEP 02-0175) which was subsequently withdrawn by letter dated January 17, 2003 (Serial: BSEP 03-0013). provides a copy of the Form OAR-1 Owner's Activity Report for the containment inspections performed in accordance with the ASME Code,Section XI, Subsections IWE and IWL during Unit 2 Refueling Outage 15.

Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor -

Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, Edward T. ONeil Manager - Support Services Brunswick Steam Electric Plant WRM/wrm

Enclosures:

1. Owner's Activity Report - OAP-i Report for B216R1 Refueling Outage, Revision 1

2. Leakage Evaluation for Bolted Connection at Valve B32-FO31B

3. Owner's Activity Report - OAR-i Report for B216R1 Refueling Outage Containment Inspections

Document Control Desk BSEP 03-0137 / Page 3 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Division of Boiler and Pressure Vessel North Carolina Department of Labor ATTN: Mr. Jack Given, Assistant Director of Boiler & Pressure Vessels 4 West Edenton Street Raleigh, NC 27601-1092

BSEP 03-0137 Enclosure I Owner's Activity Report - OAR-1 Report for B216R1 Refueling Outage, Revision 1

CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 OWNER'S ACTIVITY REPORT OAR-1 REPORT FOR B216R1 REFUELING OUTAGE REVISION I Prepared By: Date 9 03 NDE / Snubber &Support Progr4n Manager Reviewed By: ?Sa~

Pressure Test Program Manager Date 7-2Z3-O3 Reviewed By: ,

/

'.6 / '

A RepairlReplacement Program Manager Date 9/ a-0a Reviewed By: lknvy Date? 5 3

,Aorized Nuclear Inscrvice Inspector

INTRODUCTION This report represents a summary of the Inservice Inspection (ISI) activities performed at the Carolina Power and Light Company's Brunswick Steam Electric Plant (BSEP) Unit 2 during the Spring 2003 refueling outage.

The examinations and testing performed during this timeframe were for credit during the second inspection period of the Third Inspection Interval.

Examinations and testing were performed to satisfy the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Inspection Program B, 1989 Edition with no addenda.

During the refueling outage, ASME Code Category B-D and R-A components were identified as having less than 90% coverage. A relief request will be submitted prior to the end of the Inspection Interval for examination coverage.

In accordance with requirements of Code Case N-532, which has been approved for use at the Brunswick Station, enclosed is the Owners Activity Report (OAR-1 Report).

FORM OAR-1 OWNER'S ACTIVITY REPORT Report number 2-03-B216R1_

Owner _Carolina Power &Light Company, PO Box 1551, Raleigh, North Carolina (Name and Address of Owner)

Plant __Brunswick Steam Electric Plant, PO Box 10429, Southport, North Carolina_

(Name and Address of Plant)

Unit No. 2 Commercial Service Date 1113/75 . Refueling outage no. _B216RI (if applicable)

Current inspection interval. 3rd (1st. 2nd, 3rd, 4th, other)

Current inspection period -_2nd (Ist, 2nd, 3rd)

Edition and Addenda of Section Xl applicable to the inspection plan _1989 edition with no addenda_

Date and revision of inspection plan April 16, 2003 ISI Program Plan revision 8 Edition and Addenda of Section Xl applicable to repairs and replacements, if different than the inspection plan _

CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct and that the examinations, tests, repairs, replacements, evaluations and corrective measures represented by this report conform to the requirements of Section Xi.

Certificate of Authorization No. NIPS Expiration Date WJA (if applicable)

Signed Qr's ro cc, e MTA Date 320o3 Ovincr or Owvn Is DcsigncTt CERTIFICATE OF INSERVICE INSPECTION 1,the under signed, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of North Carolina and employed by lHanford Steam Boiler__ _ of Connecticut have inspected the items described in the Ovner's Activity Report during the period A'- 3 '- 0 I to

• 24- 03 . and state that to the best of my knowledge and belief, the Owner has performed all of the activities represented by this report in accordance with the requirements of Section Xi.

By signing this certificate neither the Inspector nor his employer makes any warrantee, expressed or implied, concerning the tests, repairs, replacements, evaluations and corrective measures described this report. Furthermorc, neither the Inspector nor his employer shall be liable in any manner for an personal injury or property damage or a loss of any kind arising from or connected with this inspection.

G > /J /:& 4 Commissions NC-1433, A.N.I.B.C._

Inspector's Signature National Board, State, Province and Endorsements Date  ? 5

TABLE 1 ABSTRACT OF EXANUNATIONS AND TESTS

TABLE 1 NOTES.

The following notes correspond to the numbers referenced in Table I of the OAR-1 Report:

1. Examination categories B-B, B-H, B-K-1, B-N-3, B-L-1, B-M-1, C-F-1, C-G, D-A, D-C do not apply to the Brunswick Station or are not required for the Third Inspection Interval.

2. Some or all examinations in this category may be deferred until the end of the inspection interval.

3. Examination category B-F and B-J have been subsumed by Category R-A to reflect approval of a Class 1 Risk Informed ISI Program. This was implemented with the commencement of the Second Inspection Period and the total number of examinations for the remaining periods and interval reflect Relief Request RR-27 and NRC Safety Evaluation dated 2/17/2000.

4. The examinations under this examination category are event related. They are only required if a subject pump or valve is disassembled during a maintenance activity.

5. Item number B7.80 of this category includes a requirement to examine CRD bolting if a CRD is disassembled. In accordance with relief request RR-04 which implemented Code Case N-547, there is no longer a requirement to examine this bolting.

6. This category has only 2 items and is covered by Relief Request RR-21.

7. Only 9 HPCI studs are accessible for examination. The remaining bolts are exempted from examination per Relief Request RR-2.

TABLE 2 ITEMS WTH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Note: for examination category B-P, the relevant condition was leakage at bolted connections. In accordance with the provisions of relief request RR-17, leakage at bolted connections required an evaluation using the criteria of ASME Code Case N-566-1.

TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE jReplaeeto

-tCorrective '- Item

.; ,'r lass . ...

Rvts SMeasure':2- Desraptioii Repair of 3 Repair Piping through wall No 3/16/03 191267 leak on line 2-SW-103-24-157 Replacement of 3 Replacement Piping component blind flange and No 1/7/03 322150 bolting per EC

Revision Summary

• Administrative corrections found during review

BSEP 03-0137 Enclosure 2 Leakage Evaluation for Bolted Connection at Valve B32-FO31B

ATTACHMENT 10 Page 1 of 1 Integrity Disposition Data Sheet for Pressure Retaining Bolting Component: 2-B32-F031 B Date: 3/27/03 OPT-80.1, Figure 4

1. Location and description of Bolted Connection Leakage:

B32-F031 B, Recirc Loop B, Discharge valve; El 015, DW Az 291 The valve was observed leaking 1/16" steady steam form the body to bonnet bolted connection.

2.

References:

C-02409 (shs 00019-1 and 0020-1, Tech Manual FP-50274, DBD-02, D-02548 sh 0002B, D-02548 shOO2A, Y2 FP-5363, D-02518 (shOO01 A and 0001 B)

3. Number and Age of Bolts:

28 studs and nuts greater than 10 years

4. Bolt and component material:

Body to bonnet studs Al 93 grade B7 Bonnet nuts A194 grade 8 Valve Body/Bonnet A351 grade CF8

5. Corrosiveness of the process fluid that is leaking:

The process fluid during the performance of OPT-80.1 is reactor coolant. During normal operation, the reactor coolant is demineralized water with hydrogen and zinc addition. As such, the coolant is slightly acidic to close to neutral PH. With a loss of the hydrogen addition, the pH of the coolant will become more acidic. Since interruptions of the hydrogen addition are infrequent, the corrosiveness of the reactor coolant is minimal because of its generally neutral environment.

When the unit is shutdown, the coolant will become acidic. During this condition, the corrosion rate is slightly higher. However during this short period of time, this acidic condition would not compromise the integrity of these bolted connections.

In summary, the susceptibility of the bolting to corrosion because of the reactor coolant leakage is minimal. As such, the integrity of the bolted connection would not be compromised.

6. System function of the leaking bolted connection:

Recirc discharge valves close to isolate the loop on a LOCA ECCS signal to prevent LPCI flow diversion, pressure retaining boundary, isolation for pump and valve maintenance.

7. Leakage history.

2-B32-F031 B body to bonnet leak has leaked the last 4 hydros Evaluation:

2-B32-F031 B valve was observed leaking 1/16" steady stream during the RPV leakage test (OPT-80.1). The bolted connection General Visual Inspection data sheet found no reportable indications.

This valve historically has seen a steady 1/8" steam and has been visually inspected during heatup to seal for normal plant operation. Historical retorquing of the body to bonnet bolts for this valve has not reduced the leakage. Corrective actions were not required during B2161R1.Based on the review performed, the leaking bolted connection was not predicted to fail during the next refueling cycle from bolting corrosion resulting in loss of structural integrity of the mechanical joint.

System Engineer: .  ; 't As Date: /67/*5

.35- C,.f /910 OPT-80.1 I Rev. 46 l Page1 f1

BSEP 03-0137 Enclosure 3 Owner's Activity Report - OAR-1 Report for B216R1 Refueling Outage Containment Inspections

- AlTACHMENT 1 Page 1 of 2 Code Case N-532 Form OAR-1, Owner's Activity Report FORM I . l^

OAR-1 OWNER'S ACTIVITY REPORT .

Report Nunber CIP-B21 SR1 Owner Cuoina Power & Ublt Conpany dWa Progress Energy Carorhas. Inc.. PO Box 1551. Raleigh. North Carolina (Name and Addrew d Owner)

Plant BnrwwckSteam Eetric Plant PO Box 10429, Souofx to Cardona (Name and Aftess d Plant) tht No. 2 Commervla! Service Date November 1975 Refueln g Outage No. B216R1 (Ifapplicable)

Currenrt kIspection Wnerval Firt Contalrinent kwspection Intrva (&*,section IWE & IWL Only)

(I'. 2"'. 3', 4',other)

Current Inspection Period 2' Inspection Period (1". 2d. 3)

Edition and Addenda dSection XI Apliao te Ipection Plan 1992 Edtion w/ 1992Addonda Date and Revision of Ispection Plan OBNP-TR 002 (RS 1A3 R5-2i502 and -12f274V0)

EdiMon and Addenda d Section XI Applcable to Repairs and Replacements, I different that te Inspection Plan NA CERTIFICATE OF CONFORMANCE I certify that the statemensr made hi ts Owners Activity Report atr correct and that the examirnat5ons. ests, repairs, replacements, evaluatiorn. and correc measures represented by this report conform to the requirements d Section Xl.

Cetifcate d Authoilation No. N/A Expiration Date NWA Sikedr¢ A f 06 1~E OFaulbrmt Perftmvice Supervisor Date (34we or Ownets 504", TUe CEFRIFrCATE OF INSERVICE ISPECTION 1.te urdorsgnod holding a valid co inssion Issued by toi National Board d Bolor and Pressure Vessel Ispectors; and tie Stato or Province of North Caolna and eployd by Harford Stem lor specion ad Isurance Company od Hartford. Connectict have Inspected te koms dscribod hIths Ownr's Acdvty Report durIng te period Y27/01 to Al/l 3 , and state that bo te best of my kowlyedge and belief, the Owner has performed al d the activities rpresented by this report Inaccordance with the re qrmts of Section )U.

By Iigng this certificate neither th Inspector nor his employermadks any waranty. exprssed or knprd. concednngthe examinatiors, Posts, ropais. replacements, evaluations and correctv measures described InNis report. Futermore, neither th Inspector nor his employershall be lablo Inany m ewr for ay persona Inury or property damage ora lss of any kId arising from or connected vthh Inspection.

Commissions NS-9557-AMBC:NC1433 e knspectoes Signature National Board, State, Province a Endorsemedt Datea*.

This loom (EO0127) may be obtained for the Order Dept, ASME. 22 Law Drive. Box 2300, airfield. NJ 07007-2300 OENP-16 I Rev. 43 1

ATTACHMENT 2 Page 2 of 2 Code Case N4-532 Tables 1,2, and 3 Note: This Ownees Acvy Report is only applcable to te Containent Inspection Program (Subsection WE &IYYL) and does not address Class 1.

Zand3carrporens.

TABLE 1 ABSTRACT OF EXAMNATIONS AND TESTS Tota Total Total Total Examinations Ecamnzbons Examiations Ebminations Credd (%)To Examhnation Required For Credited For Credfted () Date For Cator y The Interval Mis Period ForThIs Period lbs Interval Remarks E-A 783 0 0% 0% Exam Category E-A was revised to reschodie (261/Perio exams from l216R1 totheB217R1 otage In support f te deferral of the UnIt 2 Type A Test

_____________ ~~~~~~~~~~~~~(ILR O).

E8 MWA NIA NWA WA This Category is rot beig kiprented as alowed

_________ by~~~

10 CFR 5055 SU(2b)(2XC).

E-C 48 0 0% 0% Exam Category E-C was revised to reschedule

. (18Perid) exams from B21 SRI to the B217R1 ageo In support d the deferral of th UnIt 2 Type A Test nILRnT.

ED 3 0 0% 0% Exam CategoyE-D was revisd to resedule (1/Period exams tmn 8216RI to the 1217R1 outage in suppot of te deferral d te UnIt 2 Typo ATest E-F NWA KIA N/A WA This Categoery Isnot beng ktnomented as slowed by 10 CFR 50SSa(b)(2)0x)xC).

E4 27 0 0% 0% Exam Category E-4 was revised to rescheadte 9/Period) exams frm 8216R1 lo the B217R1 outage h E_P NiA WIA WA -NA

).

support fthe deferral of the Unht

__T 2 Type ATest L*A NA 0 0% WA The examinabon frequency for this Category is once every fov years. Inspection ntorval Isnot apprcable bo ths Categor, L-8 WA NA WA NIA The Unit 2 contarinent does nat have a post-

_ _ __ __ _ _ ._ _ _ _ _ -_ _ _ _ _ _ tens in g M term TABLE 2 ITEMS WITH FLAWS OR RELEVANT cNDmoNS THAT REOUIRE EVALUATION FOR CONIMNUED SERVICE Flaw Flawor RelvMConanFou Exam~etit" ttor tm Cncerization Dur Sdcodded Section Xl Category Nurber Descxton Qo(IWA3r000) ERa bn orTest (es orNo)

NoneNone Nonone None TABLE 3 ABSTRACT OF REPAIRS. REPLACEMENTS, OR CORRECTIVE MEASURES REaUIRED FOR CONTINUED SERVICE flaw or Relevant Condition Found Repair. During Sdedtlod Replacemema Section)() Repebw Code or Corrective Examiiation or Date Reptacement Class Measure hem Deserffl Dosc dWork Test Yes or No) Conmpeted Plan Nunber None None None I WA No WNA IOENP-16 I Rev. 43 I I