ML20235T161
| ML20235T161 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/02/1987 |
| From: | Richey R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313 NLS-87-198, NUDOCS 8710090277 | |
| Download: ML20235T161 (8) | |
Text
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CP&L I
Carouna Power & LigM Company I
SERIAL: NLS-87-198 OCT 0 21987 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 IGSCC INSPECTION PLANS Gentlemen:
By letter dated June 12, 1986, the NRC requested that Carolina Power & Light Company (CP&L) submit plans for Integranular Stress Corrosion Cracking (IGSCC) Inspections at the Brunswick Steam Electric Plant, Unit No. 2 (BSEP-2) at least three months prior to the start of the next refueling outage. The information submitted herein describes plans for inspection and/or modification of the recirculation piping and any other service sensitive austenitic stainless steel piping which maintains temperatures above 200*F during operation. These inspections and mitigative actions will be performed during the upcoming Reload 7 outage at BSEP-2, currently scheduled to begin on January 2,1988.
The inspections will be performed in accordance with Draft NUREG-0313, Revision 2, as j
previously discussed with members of your staff.
l l
The scope of actions to be taken have been divided into four categories: (1) Draf t i
NUREG-0313, Revision 2, Inspections; (2) Mechanical Stress Improvement Process; l
(3) Pipelock Repair Contingency; and (4) Hydrogen Water Chemistry Implementation.
Each category is discussed below.
DISCUSSION 1
(1)
Draf t NUREG-0313, Revision 2, Inspections The BSEP-2, Reload 7 inspection program will include ultrasonic inspection of I
the austenitic stainless steel welds in accordance with the requirements of Draf t NUREG-0313, Revision 2, and the requirements specified in Safety Evaluation Reports dated June 12,1986 and November 5,1986 regarding the BSEP-2, Reload 6, ICSCC inspection program.
Per the requirements, CP&L has classified the " service sensitive" weldments into the seven categories as defined in the draf t NUREG. Table i provides a listing of the welds by category. The BSEP-2, Reload 7 inspection plan, based on these classifications, is as follows:
a)
Categories A, B, and G Weldments Category A welds were inspected during the Reload 6 outage. BSEP-2 has no welds in Categories B and G. No inspections are planned.
B710090277 871002 PDR ADOCK 05000324 G
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411 Fayetteville street e P O Box 1551
- Rateign N C 27602 IC E. Z R Zi E T."2iE Z IIA M HUIll M Z 3 h 7 E irca
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- Document Control Desk NLS-87-193 / Page 2 b)
Category C Weldments The 58 welds under this classification received Induction Heating Stress Improvement (IHSI) application during Reload 6 and were inspected by ultrasonic testing (UT) prior to restart. Table 2 provides a listing of the welds to be inspected during the Reload 7 outage.
Personnel performing the IGSCC inspections will be qualified in accordance l
with the EPRl/BWROG/NRC requirements. The Company plans to use the automated GE SMART UT system for inspections where physical clearances allow.
l l-c)
Category D Weldments l
This category contains the inconel butter nozzle welds, safe-end-to-thermal-sleeve crevice welds, decontamination connections, and the upstream side of the tie in to Reactor Water Cleanup System which was replaced during the Reload 6 outage. Table 3 provides a listing of the welds to be inspected during the Reload 7 outage.
l These examinations will be performed by qualified personnel using EPRI qualified techniques. The GE SMART UT system will be used where i
physical clearances allow, d)
Category E Weldments There are currently 39 weld overlay repairs on BSEP-2. Five of these repairs were applied in 1983 and upgraded during Reload 6. At the end of the current cycle, these repairs will have been in service for two fuel i
cycles. The remaining 34 were applied in 1986 during Reload 6 and have been in service only one cycle.
i i
Thirty-two of the repairs, including the five upgraded during Reload 6, meet the standard overlay design criteria and four meet the designed overlay criteria described in Draft NUREG-0313, Revision 2. The Company plans to upgrade three designed overlays (2-B32-28" A-4, B-3, and B-4) to a standard design during the upcoming BSEP-2, Reload 7 outage. Upgrading J
these weld overlay repairs consists of adding length and thickness as required and performing surface finishing.
In addition,21 weld overlay repairs, including the five applied during 1983 and the three to be upgraded in the Reload 7 outage, will be reinspected by ultrasonic testing. Table 4 provides a listing of these weld overlays. These i
examinations will be performed by qualified personnel using EPRI qualified l
techniques. The GE SMART UT system will be used if physical clearance l
allows.
I e)
Category F Weldments Results of inspections performed during Reload 6 revealed small axial indications in each of the 28-inch suction-nozzle-to-safe-end welds. These two inconel butter welds, listed in Table 5, will be inspected during the upcoming Reload 7 outage. These examinations will be performed by I
qualified personnel using EPRI qualified techniques. The GE SMART UT I
system will be used if physical clearance allows.
i E_-.__-----------
J
' Document Control Desk NLS-87-198 / Page 3 (2)
Mechanical Stress improvement Process The Mechanical Stress Improvement Process (MSIP) will be performed on selected inconel butter welds of reactor pressure vessel nozzles. Industry accepted rnethods for the O'Donnell and Associates, Inc. patented process will be used. The welds will be ultrasonically inspected before and after MSIP.
(3)
Pipelock Repair Contingency Based upon results of the inspections of inconel butter welds to be performed during the upcoming BSEP-2, Reload 7 outage, CP&L plans to repair any of these inconel butter welds found to be unacceptable for continued operation, with a pipelock designed by O'Donnell and Associates, Inc.
(4)
Hydrogen Water Chemistry Implementation Carolina Power & Light Company has started engineering and installation of a Hydrogen Water Chemistry Control System and plans to make the system connections during the BSEP-2, Reload 7 outage. Design and installation of the system will be performed in accordance with EPRI Report NP-4500-SR-LD,
" Guidelines for Permanent BWR Hydrogen Water Chemistry Installation." Based on the results of the pre-implementation hydrogen water chemistry test conducted in December 1986 - January 1987, CP&L does not anticipate the need to request Technical Specification changes to accommodate the installation and operation of the Hydrogen Water Chemistry System.
ADDITIONAL ACTIONS The results of the inspection, the specific scope of the MSIP program, and pipelock installation (s), if required, and a description of any further corrective actions will be submitted prior to BSEP-2 start-up.
Please refer any questions concerning this submittal to Mr. Sherwood R. Zimmerman at (919) 836-6242.
Yours very truly,
/77% M %
Ri ey O
ger Licensing and Nuclear Fuel BAT /bmc (5284 BAT)
Enclosures cc:
Dr. J. Nelson Grace Mr. W. H. Ruland Mr. E. D. Sylvester
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TABLE 2 CATEGORY C WELDS TO BE INSPECTED BSEP-2 RELOAD 7 OUTAGE WELD NUMBERS 2-B32-28" A-2 2-B32-22" AM-1 2-B32-12" AR-Al 2-B32-28" A-3 2-B32-22" AM-2 2-B32-12" AR-A4 2-B32-28" A-5 2-B32-22" AM-3 2-B32-12" AR-B1 l
2-B32-28" A-6 2-B32-22" AM-6 2-B32-12" AR-B4 2-B32-28" A-12BC 2-B32-12" AR-D2 2-B32-28" A-15BC1 2-B32-12" AR-D3 2-B32-28" B-2 2-B32-12" AR-El 2-B32-28" B-6 2-B32-12" BR-Fi 2-B32-28" B-12BC1 2-B32-12" BR-H1 2-B32-28" B-15BC1 2-B32-12" BR-H3 2-B32-28" B-16 2-B32-12" BR-31 2-B32-12" BR-34 2-B32-12" BR-K 1 2-B32-12" BR-K4 l
l l
l (5284 BAT /lah)
L__-.____--
_ _ _ _ _ _ _ _ _. _ _ __J
TABLE 3 CATEGORY D WELDS TO BE INSPECTED BSEP-2 RELOAD 7 OUTAGE WELD NUMBER 2-B32-28" A-9BC1 Decon. Connection 2-B32-28" B-9BC1 Decon. Connection 2-B32-12" AR-A5 Recirc. Discharge 2-B32-12" AR-B5 Recirc. Discharge 2-B32-12" AR-C5 Recirc. Discharge 2-B32-12" AR-D5 Recirc. Discharge l
I 2-B32-12" AR-E5 Recirc. Discharge l
l 2-B32-12" BR-F4A Safe-End/ Safe-End Extension I
l 2-B32-12" BR-K4A Safe-End/ Safe-End Extension 2-B32-12" BR-F5 Recirc. Discharge 2-B32-12" BR-G5 Recirc. Discharge 2-B32-12" BR-H5 Recirc. Discharge 2-B32-12" BR-35 Recirc. Discharge 2-B32-12" BR-K5 Recirc. Discharge 2-E21-10" N-5A Core Spray 2-E21-10" N-5B Core Spray 7-B21-4" N-8A Jet Pump Instrumentation 2-B21-4" N-8B Jet Pump Instrumentation N2D @ 120' Thermal Sleeve Crevice N2] @ 300*
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(5264 BAT /lah)
I TABLE 4 CATEGORY E WELDS TO BE INSPECTED BSEP-2 RELOAD 7 OUTAGE 2-B32-78" A-4 2-B32-12" BR-G2 2-B32-28" B-3 2-B32-12" BR-G3 2-B32-28" B-4 2-B32-12" BR-G4 j
2-B32-28" B-5 2-B32-12" BR-32 2-B32-12" BR-33 2-B32-22" BM-1 2-B32-12" BR-K2 2-B32-12" BR-K3 2-B32-12" AR-A2 2-B32-12" AR-C1 2-B32-4" A-ll 2-B32-12" AR-C2 2-B32-4" B-ll 2-B32-12" AR-C3 2-B32-12" AR-C4 2-B32-12" AR-D1 2-B32-12" AR-E4 i
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i (5284 BAT /lah) i
___ _ _ _ _ _ _ -. _ _ _ _ _ __. __ ___ _ _J
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1 TABLE 5 I
CATEGORY F WELDS TO BE INSPECTED BSEP-2 RELOAD 7 OUTAGE WELD NUMBERS
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