ML20239A699

Addendum 1 to Rev 2 to Integrated Reactor Vessel Matl Surveillance Program (Addendum)

ML20239A699
Person / Time
Site:	Oconee
Issue date:	11/30/1987
From:	Gross L BABCOCK & WILCOX CO.
To:
Shared Package
ML15244A375	List: ML20239A699
References
BAW-1543A-ADD, BAW-1543A-ADD01-R02, BAW-1543A-ADD1-R2, NUDOCS 8712300004
Download: ML20239A699 (21)

Text

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BAW-1543A, Rev.2, Addendum 1 November 1987

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BAW-1543A. Rev. 2 '

Addendum 1 November 1987 INTEGRATED REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM (ADDENDUM) by L. B. Gross Prepared for B&W Owners Group Materials Committee Arkansas Power & Light Company Duke Power Company Florida Power Corporation GPU Nuclear Croporation Sacramento Municipal Utility District Toledo Edison Company B&W Document No. 77-1168618-01 (See section 3 for document signatures)

Prepared by BABC0CK & WILC0X Nuclear Power Division P. O. Box 10935 Lynchburg, Virginia 24506-0935

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[pn anc c., UNITED STATES J. H. Tayine y ) j #(- p, NUCLEAR REGULATORY COMMISSION r,, ( ,..y WASHINGTON. D. C. 20555 h(f Q$ jgg7 g sf / September 18, 1987

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Mr. J. H. Taylor Manager, Licensing Service Babcock & Wilcox 5315 Old Forest Road P.O. Box 10935 Lynchburg, Virginia 24506-0935

SUBJECT:

REVIEW 0F PROPOSED REVISION TO THE BABC0CK & WILC0X OWNERS' GROUP INTEGRATED REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM.

The NRC staff has completed its review of the proposed changes to the Babcock & Wilcox Owners Group (BWOG) integrated reactor vessel material surveillance program which was submitted in letters from you to T. E. Murley dated August 6, 1987 and August 27, 1987. The enclosed safety evaluation contains the results of the NRC staff's review which concludes that the proposed changes are acceptable.

If you have any questions regarding this evaluation please contract Byron Siegel the NRC staff's coordinator for the BWOG programs at (301) 492-7764.

In B/ronSie 1, Lead Project Manager for BWOG Programs

Enclosure:

As stated

ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REVIEW 0F A PROPOSED REVISION TO THE B&W OWNER'S GROUP INTEGRATED SURVEILLANCE PROGRAM TAC NO.# 65927 MATERIALS ENGINEERING BRANCH l DIVISION OF ENGINEERING AND SYSTEMS TECHNOLOGY Backaround The Babcock & Wilcox (B&W) Owners Group proposed an integrated reactor vessel surveillance program for Oconee, Units 1, 2 and 3; Arkansas Nuclear One, Unit 1; Ranch Seco; Three Mile Island, Unit 1; Three Mile Island, Unit 2; Midland, Unit 1; Davis Besse, Unit 1; and Crystal River, Unit 3 plants. In this program, reactor vessel surveillance capsules from all the participating owners, except Consumers Power Co., were to be irradiated inside the reactor vessels at Davis Besse and Crystal River. The integrated surveillance program was documented in Report BAW-1543, Rev. 2, February 1984, " Integrated Reactor Vessel Material Surveillance Program." The staff's review of the integrated program is documented in a letter from C.0. Thomas to J. H. Taylor, dated March 15, 1985. The staff approved the integrated program for all participating plants, except Three Mile Island, Unit 2 and Midland, Unit 1.

The regulatory requirements for an integrated material surveillance program are documented in 10 CFR 50, Appendix H. This appendix indicates that the material surveillance program is required to monitor changes in the fracture toughness properties of ferritic reactor vessel beltline materials resulting from exposure of these materials to neutron irradiation and the thermal environment.

Discussion In letters to T. E. Murley dated August 6, 1987 and August 27, 1987, B&W, acting for the owners group proposed changes to the owners group integrated reactor vessel surveillance program. The changes include a revised surveillance capsule insertion and withdrawal schedule and deletion of Capsule TMI-1A from the program.

The changes to the capsule withdrawal schedule were needed because of changes to the end-of-life calculated neutron exposures of the participating vessels and the calculated neutron exposures at the capsule holder positions. Changes in calculated neutron exposures result from plants using low leakage cores and more accurate neutron fluence determinations. Except for TMI-1, end of life neutron fluence values were previously reported in Peport BAW-1895,

" Pressurized Thermal Shock Evaluation in Accordance with 10 CFR 50.61 for Babcock & Wilcox Owners Group Reactor Pressure Vessels." TMI-1 values were modified consistent with the results of Report BAW-1901, " Analysis of Capsule TMI-1C GPU Nuclear Three Mile Island Nuclear Station Unit 1," March 1986.

The B&W method of calculating neutron fluence and owners group plants end of life neutron fluence values were reviewed by the staff in its evaluation of the PTS issue and owners group surveillance capsules.

The Owners Group proposes that Capsule THI-1A be destructively examined to roqualify the TMI-2 B&W Owners Group surveillance capsules. TMI-1A was one of six capsules removed from the THI-2 reactor. Capsules THI-1A and TMI-2 LG2 '

(both in the ZY holder tube location) represent the " worse case" capsules based on the condition of the temperature monitors obtained by radiography. - 0 These two capsules experienced a similar thermal environment, which appears to I be hotter than the other holder tube locations. The TMI-1A capsule contains

• Charpy V notch and tensile specimen. Since the THI-2 LG2 capsule contains Charpy V notch, tensile and compact fracture toughness specimens, the TMI-2 LG2 capsule will provide substantially more useful fracture t6ughness data than the TMI-1A capsule.

Capsule TMI-1A contains weld metal WF-25, which is one of the materials in the '

beltline region of TMI-1. In addition to capsules TMI-1C and TMI-1E weld metal WF-25 is also contained in Owners Group Capsules CR3-LG1, THI-2LG2 and TMI-2LG1. The Owners Group capsules also contain weld metal SA-1526, which was made with the same heat of filler wire used to fabricate WF 25 weldments.

The filler wire contributes residual elements to the weldment. Staff studies indicate that the residual elements in the filler wire contribute to the neutron irradiation damage to the weldment. Since SA-1526 and WF-25 weldments were made with the same filler wire, the SA-1526 surveillance welds will provide data on the effect of neutron irradiation on WF-25 weld metal.

Although the weld metal in TMI-1A will not be irradiated and tested, as planned, the owners group program contains other sources of weld metal, which can be used to replace the THI-1A capsule weld metal.

Conclusions

1. Since Owners Group capsules can provide more useful fracture toughness data than the TMI-1A capsule and the effect of neutron irradiation on TMI-1A weld metal can be evaluated from material in other surveillance capsules, the TMI-IA capsule may be used to requalify the TMI-2 Owners Group surveillance capsules. '

2. The integrated reactor vessel materials surveillance progrn documented in Report BAW-1543A, Rev. 2 and revised in accordance with B&W letters dated August 6,1987 and August 27, 1987 will be capable of monitoring the effect of neutron irradiation and the thermal environment on the fracture toughness of the ferritic reactor vessel beltline materials in the plants participating in the integrated material .

surveillance program.

3. Based on conclusions 1 and 2 above, the changes to the integrated surveillance program documented in B&W letters dated August 6,1987 and August 27, 1987 are acceptable.

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Babcock & Wilcox Nuclear Power Division a McDermott company 3315 Old Forest Road October 20, 1987 P o. Box 10935 Lynchburg, VA 24506 0935 (804) 385 2000 Mr. D. N. Miskiewicz Florida Power Corporation P.O. Box 14042 St. Petersburg, FL 33733

Subject:

Capsule Identification for Insertion in CR-3 During Cycle 6 Refueling Outage

Reference:

BAW-1543, Rev. 02, " Integrated Reactor Vessel Material Surveillance Program (Addendum), dated July 1987.

Dear Mr. Miskiewicz:

As youthus year, know the capsule withdrawal schedule was changed this BAW-1543 was revised with the issuance of the Addendum, referenced above. The NRC approved this change in capsule insertion in their SER of Sept 21, 1987 with a change needed to requalify the capsules removed from the TMI-2 vessel, that being the deletion of TMIl-A from the schedule.

Thus, the capsules to be withdrawn and inserted during CR-3 cycle six outage are as per Table 2-1, page 2-2 of BAW-1543, Addendum 1, with the following exception.

from the schedule was included in This removal of TMIl-A capsule the SER released by NRC.

Capsule TMIl-A was opened to provide data to requalify the B&WOG research capsules for re-insertion. Thus a replacement capsule was needed to fill the remaining space in capsule holder YX TOP.

Capsule TMI2-D was selected to be used as the filler or dummy capsule for insertion in YX TOP and is not considered to be a capsule needed for the Integrated Surveillance Program.

If there are questions please call me at 804-385-2208.

Very truly yours, 4&& J. F. Walters Project Manager Owners Group Engineering Services cc: Scott Stuart - CR Site

[ R. J. Finnin - CR B&W Site

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CONTENTS l

Page

1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1

2. INTEGRATED REACTOR VESSEL SURVEILLANCE PROGRAM . . . . . . . . . . 2-1

3. CERTIFICATION . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 List of Tables Table 1-1. Reactor Vessel Neutron Exposure . . . . . . . . . . . . . . . . 1-2 1-2. RVSP Capsule Neutron Exposure . . . . . . . . . . . . . . . . . 1-2 2-1. Capsule Insertion and Withdrawal Schedule for Crystal River Uni t 3 . . . . . . . . . . . . . . . . . . . . . . 2-2 2-2. Capsule Insertion and Withdrawal Schedule for Davis-Besse . . . . 2-5 2-3. Summary Status of Surveillance Capsules . . . . . . . . . . . . 2-7 List of Fioures Figure 2-1. Crystal River-3 IRVSP Schedule . . . . . . . . . . . . . . . . . 2-9 2-2. Davis-Besse IRVSP Schedule . . . . . . . . . . . . . . . . . . . 2-10

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Babcock & WHcox a McDermott company

1. INTRODUCTION This addendum to BAW-1543, Rev. 2, provides a revised insertion and withdraw-al schedule for surveillance capsules in the Crystal River-3 and Davis-Besse reactors. Extensive changes are made in the irradiation schedule starting with the next refueling outages:

o Crystal River-3, end-of-cycle 6, fall 1987 e Davis-Besse, end-of-cycle 5, spring 1988 The changes in schedule were required to provide for the following changes:

e Recalculation of neutron exposure of the vessels.

\

e Recalculation of neutron exposure of the capsules.

The end-of-life calculated neutron exposures of the participating vessels that are the bases for the schedule are shown in Table 1-1. The calculated neutron exposure of the capsule holder positions (beyond the current cycle) are shown in Table 1-2. Changes from the previously used values are due to more accurate determinations as a result of actual fluence determinations and a number of plants using low leakage fuel cycles. Except for TMI-1, these end-of-life fluence values are identical to that reported in BAW-1895,

" Pressurized Thermal Shock Evaluations in Accordance with 10CFR50.61 for Babcock & Wilcox Owners Group Reactor Pressure Vessels." TMI-1 values were modified consistent with the results of BAW-1901, " Analysis of Capsule TMll-C GPU Nuclear Three Mile Island Nuclear Station - Unit 1," March 1986.

The revised schedules are shown in section 2 of this report. These revised schedules will also be presented in BAW-1543, Rev. 3, which is currently in preparation.

~

Babcock & WHcox a McDermott company

l l

Table 1-1. Reactor Vessel Neutron Exposure Calculated Peak Inside Surface Flyence Nuclear Plant at End-of-Life (32 EFPY), n/cm' Oconee-1 1.16E19 Oconee-2 1.20E19 TMI-1 0.80E19 Crystal River-3 0.96E19 ANO-1 1.10E19 Oconee-3 1.56E19 Rancho Seco 0.91E19 Davis-Besse 1.70E19 Table 1-2. RVSP Caosule Neutron Exposure Fluence, n/cm2 / cycle Crystal River-3 Davis-Besse Fuel High Flux (10.90) Low Flux (26.90) High Flux (10.90) Low Flux (26.90)

Cycle locations locations locations locations IA 1.74E18 1.13E18 3.19E18 2.08E18 1B 1.16E18 0.76E18 NA NA 2 1.13E18 0.74E18 3.16E18 2.06E18 3 2.20E18 1.43E18 2.92E18 1.90E18 4 2.29E18 1.49E18 3.76E18 2.45E18 5 3.29E18 2.15E18 3.41E18 2.22E18 6 and 2.22E18 1.45E18 3.27E18 2.13E18 beyond 1-2

2. INTEGRATED REACTOR VESSEL SURVEILLANCE PROGRAM l

l l

The revised insertion and withdrawal schedule for irradiation capsules in Crystal River-3 is presented in Table 2-1 and Figure 2-1. The revised insertion and withdrawal schedule for irradiation capsules in Davis-Besse is presented in Table 2-2 and Figure 2-2. A summary of the status of all I

irradiation capsules currently in the integrated reactor vessel survei'ilance program is presented in Table 2-3.

I 2-1 Babcock & Wilcox a McDermott company

l Table 2-1. Capsule Insertion and Withdrawal Schedule for l Crystal River Unit 3 Holder Location in I Tube Holder Tube Remove Insert Installed at Initial Fuel load XW Top CR3-B (WC)

XW Bottom CR3-D (WC)

End of First Fuel Cycle. First Part (1A1 WZ Top CR3-LG1 (WC)

WZ Bottom CR3-LG2 (WC)

ZY Top CR3-C (W)

ZY Bottom CR3-A (W)

YZ Top OC2-A (W)

YZ Bottom OCl-A (W)

YX Top OC2-E (W)

YX Bottom OC3-D (W)

XW Top CR3-B (WC) CR3-E (W)

WX Top OC3-B (W)

WX Bottom CR3-F (WC)

End of First Fuel Cycle. Second Part (IB)

No change.

End of Second Cycle YZ Top OC2-A (W) OCl-C (W)

WX Top OC3-B (W) TMIl-C (W)

End of Third Cycle No change.

End of Fourth Cycle l WZ Top CR3-LG1 (WC) None Bottom WZ CR3-LG2 (WC) None YZ Bottom OCl-A (W) OCl-B End of Fifth Cycle WZ Top None OC2-B WZ Bottom None CR3-LG2 (WC)

ZY Top CR3-C (W) OC3-F (W)

XW Bottom CR3-D (WC) TMll-B WX Top TMll-C (W) OC3-C (W)

End of Sixth Cycle YZ Top OCl-C (W) TMI2-LG1 (WC)(b)

YZ Bottom OCl-B (a) TMI2-LG2 (WC)(b)

YX Top OC2-E (W) TMll-A (W)(b)

WX Bottom CR3-F (WC) TMIl-F 2-2 Babcock & Wilcox a McDermott company

Table 2-1. Capsule Insertion and Withdrawal Schedule for Crystal River Unit 3 (Cont'd)

Holder Location in Tube Holder Tube Remove Insert End of Seventh Cycle XW Bottom TMIl-B (a) OC2-D End of Eiahth Cycle WZ Top OC2-B (a) OC3-E (W) i ZY Bottom CR3-A (W) (a) OC2-F

! YX Bottom OC3-D (W) OCl-D End of Ninth Cycle WZ Top OC3-E (W) None WZ Bottom CR3-LG2 (WC) None s YZ Top TMI2-LG1 (WC)(b) TMll-D YX Top TMll-A (W)(b) OC3-E (W) from WZ top WX Top OC3-C (W)(a) TMI2-B (WC)(b)

End of Tenth Cycle No change.

End of Eleventh Cycle XW Top CR3-E (W) TMI2-B (WC)(b) from WX top WX Top TMI2-B (WC)(a)(b) None WX Bottom TMIl-F (a) None End of Twelfth Cycle YZ Top TMll-D None YZ Bottom TMI2-LG2 (WC)(b) None End of Thirteenth Cycle l No change.

! End of Fourteenth Cycle YX Bottom OCl-D (a) TMll-D XW Top TMI2-B (WC)(a)(b) None XW Bottom OC2-D (a) None End of Fifteenth Cycle No change.

2-3 Babcock & Wilcox a McDermott company

Table 2-1. Capsule Insertion and Withdrawal Schedule for Crystal River Unit 3 (Cont'd)

Holder Location in Tube Holder Tube Remove Insert End cf Sixteenth Cycle ZY Top OC3-F (W)(a) None ZY Bottom OC2-F (a) None YX Top OC3-E (W)(a) None YX Bottom TMIl-D (a) None LEGEND (a) Capsule may not be tested upon removal.

(b) Requalified from TMI-2 irradiation.

(W) Capsule contains weld metal specimens.

(WC) Capsule contains weld metal compact fracture toughness specimens.

Babcock & Wilcox a McDermott company

Table 2-2. Caosule Insertion and Withdrawal Schedule for Davis-Besse Holder Location in Tube Holder Tube Remove Insert Installed at Initial Fuel Load WZ Top AN1-B WZ Bottom RS1-B (WC)

ZY Top TEl-B (WC)

ZY Bottom TEl-F (WC)

YZ Top AN1-A (W)

YZ Bottom AN1-C (W)

YX Top RS1-D (WC)

YX Bottom TEl-C (W)

XW Top TEl-D (WC)

XW Bottom RS1-C (W)

WX Top TEl-A (W)

WX Bottom RS1-F (WC)

End of First Cycle WZ Top AN1-B DB1-LG1 (WC)

WZ Bottom RSI-B (WC) RSI-E (W)

ZY Bottom TEl-F (WC) DB1-LG2 (WC)

End of Second Cycle YX Top RSI-D (WC) RSI-A (W)

End of Third Cvele ZY Top TEl-B (WC) TEl-E (W)

YZ Top AN1-A (W) AN1-D End of Fourth Cycle YX Top RSI-A (W)(a) AN1-F WZ Top DB1-LG1 (WC) RS1-F from WX bottom WX Top TEl-A (W) None WX Bottom RSI-F to WZ top None End of Fifth Cycle WZ Top RSI-F (WC) None WZ Bottom RS1-E (W)(a) None YZ Top AN1-D None YZ Bottom AN1-C (W) None XW Bottom RSI-C (W)(a) AN1-D from YZ top End of Sixth Cycle No change.

End of Seventh Cycle No change.

~

Babcock & Wilcox a McDermott company

Table 2-2. Capsule Insertion and Withdrawal Schedule for Davis-Besse (Cont'd)

Holder Location in Tube Holder Tube Remove Insert End of Eiahth Cycle ZY Bottom DB)-LG2 (WC) AN1-D from XW bottom YX Top AN1-F (a) None YX Bottom TEl-C (W)(a) None XW Top TEl-D (WC) None XW Bottom AN1-D None End of Ninth Cycle No change.

End of Tenth Cycle No change.

End of Eleventh Cycle ZY Top TEl-E (W)(a) None ZY Bottom AN1-D (a) None LEGEND (a) Capsule may not be tested upon removal.

(W) Capsule contains weld netal specimens.

1 (WC) Capsule contains weld metal compact fracture toughness specimens.

24 Babcock & WHcox a McDermott company

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3. CERTIFICATION This report is an accurate description of the rensed irradiation schedules for the integrated reactor vessel materie.ls surveillance program designed in accordance with the ;quirements of 10 CFR 50, Appendixes G and H.

i L. B. Gross, Principal E6gineer W k.

'Date '

Mater [ials and Structural Analysis Unit This report has been reviewed and is an accurate description of the revised irradiation schedules for the integrated reactor vessel materials surveil- '

lance program.

A fff TfW A. L.'Lowe, Jr., AdvisoFy Engineer 'Date

^

Materials and Structural Analysis Unit i

Verification of independent review, _

ff A. D. McKim, Manager O.Dll5 W }- ~~' Oste ~

f7 Materials and Structural Analysis Unf t This report has been approved for release.  !,

C.J.\ Hudson

'St M /!3!Il Dhte' Progrdm Manager 3~I Babcock & Wilcox a McDermott company

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