DCL-11-141, Response to NRC Request for Additional Information on Capsule Withdrawal Schedule Approval Request

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Response to NRC Request for Additional Information on Capsule Withdrawal Schedule Approval Request
ML113640038
Person / Time
Site: Diablo Canyon 
(DPR-080)
Issue date: 12/29/2011
From: Peters K
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-11-141
Download: ML113640038 (6)
v • d • e


Text

m Pacific Gas and

~&~ Electric Company Kenneth J. Peters Diablo Canyon Power Plant December 29,2011 VP Engineering & Projects Mail Code 104/6/603 P. O. Box 56 Avila Beach, CA 93424 PG&E Letter DCL-11-141 805.545.4888 Internal: 691.4888 Fax: 805.545.4884 u.s. Nuclear Regulatory Commission ATTN: Docu ment Control Desk Washington, DC 20555-0001 10 CFR 50, App. H Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit 1 Response to NRC Request for Additional Information on "Capsule Withdrawal Schedule Approval Request"

Reference:

1.

PG&E Letter DCL-11-122, "Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule," dated November 21,2011 In Reference 1, Pacific Gas and Electric Company (PG&E) submitted a request for approval to revise the Unit 1 reactor vessel material surveillance program withdrawal schedule to allow withdrawal of Capsule B during the Unit 1 Twenty Third Refueling Outage, which is scheduled for May 2022.

NRC Staff provided a request for additional information (RAI) via e-mail, dated December 22, 2011. The Enclosure to this letter provides PG&E's response to the NRC RAI.

PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter.

If you have any questions or require additional information, please contact Mr. Tom Baldwin at (805) 545-4720.

Sincerely,

~L/+O-Z Kenneth J. Peters rnttl4231 Enclosure cc:

cc/enc:

Diablo Distribution Elmo E. Collins, NRC Region IV' Nathanial B. Ferrer, NRC Project Manager Michael S. Peck, NRC Senior Resident Inspector Alan B. Wang, NRR Project Manager A

member of the STARS (Strategic Teaming and Resource Sharing)

Alliance Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre
  • Wolf Creek

PG&E Letter DCL-11-141 Enclosure PG&E Response to NRC Request for Additional Information on "Capsule Withdrawal Schedule Approval Request" NRC Question 1:

Issue: The ASTM E 185-70 standard practice describes the withdrawal schedule in terms of the target fluence. The requested revision is written in terms of effective full power years (EFPY) instead of target fluence.

Request: Describe the withdrawal schedule (mark-up of FSARU Table 5.2-22) in terms of the fast neutron fluence (E> 1 Me V).

PG&E Response:

Updated Final Safety Analysis Report (UFSAR) Table 5.2-22 is revised to describe withdrawal schedule in terms of fast neutron fluence (E> 1 million electron volts, MeV).

Numerical values for fast neutron fluence and lead factors are taken from latest vendor documentation. Mark-up of UFSAR Table 5.2-22 is included below.

1

TABLE 5.2-22 PG&E Letter DCL-11-141 Enclosure REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHEDULE UNIT 1 Lead Fluence at Capsule Capsule(f)(g)

Location Factor(d)

Center (n/cm2)(d)

S 320°

~3.48 2.83E+18 y

40°

~3.45 1.05E+19 T

140°

~3.45 1.05E+19 Z

220°

~3.45 1.05E+19 V

320° 2.26 1.36E+19 C(b) 140°

~3.47 1.22E+19 D(b) 220°

~3.47 1..22E+19 B(b) 40°

~3.47 3.44E+19 (projected)

A(b) 184°

+:J+1.32 Standby U

  • 356°

~ 1.24 Standby

  • X 176°

~ 1.24 Standby W

4°

~ 1.24 Standby UNIT2 Lead Fluence at Capsule Capsule Location Factor(d)

Center (n/cm2)(d)

U 56° aA-55.20 3.30E+18 X

236°

~5.39 9.06E+18 y

238.5° 4.M4.56 1.53E+19 W(e) 124°

~5.35 2.78E+19 V(e) 58.5° 4.M4.57 2.38E+19 Z(e) 304°

~5.35 2.78E+19 (a)

Approximate full power years from plant startup.

(b)

Four supplemental capsules installed at 5.86 EFPY (EOC5).

(c)

Deleted in Revision 16.

Removal Time (Plant EFPy)(a) 1.25 (Tested,1 R1) 5.86 (Tested, 1 R5) 5.86 (Removed, 1 R5) 5.86 (Removed, 1 R5) 14.3 (Tested 1 R11) 15.9 (Removed 1 R12) 15.9 (Removed 1 R12)

~

33 (planned 1 R23)

Standby Standby Standby Standby Removal Time (EFPy)(a) 1.02(Tested,2R1 )

3.16 (Tested, 2R3) 7.08 (Tested, 2R6) 11.49 (Removed, 2R9) 11.49 (Tested, 2R9) 11.49 (Removed, 2R9)

(d)

Approximate lead factors values taken from WCAP-~

17299-NP (Rev. 0) and \\A/CAP 15423 (Rev 0) for Units 1 and 2, respectively.

(e)

Capsule EFPY for Unit 2 capsules removed in 2R9; W = WA61.5, V = ~52.5, and Z =

WA 61.5 (f)

Unit 1 capsules T, U, W, X, and Z are Type 1 (base metal only)

(9)

Unit 1 capsules S, V, and Yare Type 2 (base metal and weld) 2

NRC Question 2:

PG&E Letter DCL-11-141 Enclosure Provide a list of all materials included in Capsule B that the licensee plans to withdraw during the 23fd refueling outage for Unit 1 along with the participating integrated surveillance program plant that will use the test results.

PG&E Response:

Tables 1 and 2 below are summarized from Pacific Gas and Electric Company letter DCL-92-072 to NRC, dated March 31, 1992, which describes in detail the Supplemental Reactor Vessel Radiation Surveillance Program.

At a minimum, the plants that may benefit from delaying Capsule B are listed below, since these plants have ASME SA-533, Grade B, Class 1 (High Cu) with Linde 1092 (High Cu) material (EPRI MRP-326, Draft E, "Materials Reliability Program:

Coordinated PWR Reactor Vessel Surveillance Program, (CRVSP)"):

DCPP 1 & 2, Beaver Valley 1, DC Cook 1, McGuire 1, and Salem 1 & 2.

3

Table 1 PG&E Letter DCL-11-141 Enclosure CONTENTS OF SUPPLEMENTAL SURVEILLANCE CAPSULE Sea)

Weld Metal 15 (Surrogate 27204)

Base Metal (Plate 4107-1) 15 Correlation Monitor 12 (HSST -02 Plate)

Capsule S Weld Metal (Original 27204) 3 2

(a)

Capsule B contains the following dosimetry and thermal monitors:

Dosimeter wires:

copper, iron, nickel and aluminum-0.15 percent cobalt (cadmium shielded and unshielded)

Fission dosimeters: neptunium-237 (cadmium oxide shielded), and uranium 238 (cadmium oxide shielded)

Thermal monitors: 97.5 percent Pb, 2.5 percent Ag (579°F melt point), 97.5 percent Pb, 1.75 percent Ag, 0.75 percent Sn (590°F melt point)

(b)

Broken weld metal and Heat Affected Zone (HAZ) Charpy specimens from capsule S, suitable for reconstitution Capsule B contains 52 Charpy, 3 tension and 2 Wedge opening loaded (WOL) specimens. Twelve of the Charpy Specimens are Heavy Section Steel Technology (HSST) 02 Correlation Monitor Material.

4

PG&E Letter DCL-11-141 Enclosure Table 2 COMPOSITION OF CAPSULE B TEST MATERIALS Composition (wt%)

C Mn P

S Si Ni Cr Mo Cu Supplemental Base Metal 0.25 1.36 0.011 0.014 0.24 0.56 0.48 0.13 Lower Shell Plate B41 07-1 (a)

Original Surveillance Weld 0.11 1.35 0.014 0.025 0.25 1.00 0.05 0.50 0.20 Wire heat 27204 Linde 1092 flux(b)

Surrogate Surveillance 0.13 1.23 0.014 0.009 0.21 1.00 0.05 0.54 0.22 Weld Wire heat 27204 Linde 1092 flux(c)

(a)

Lukens Steel CMTR (b)

Average of four analyses (c)

Combustion Engineering analysis 5

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