ML20247P231
| ML20247P231 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/19/1989 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19307A388 | List: |
| References | |
| NUDOCS 8909270073 | |
| Download: ML20247P231 (3) | |
Text
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' hf DUKE POWER GOMPANY m
P.O. DOX 33189 CIIAHLOTTE, N.C. 28242 Q hI
' HAL B. TUCKER Truxnowz
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(704) 373-4531 me emenmar g
. September 19, 1989 1
Y Document Control Desk US Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Duke Power Company McGuire Nuclear Station Docket Nos. 50-369, 50-370
Dear Sir:
Attached are copies of the following documents or presentation materials:
1.
McGuire Unit 2 Tube Integrity Verification Presentation.
2.
McGuire Nuclear Station Unit 2 - Review of Susceptibility to an Event like the McGuire Unit 1 Tube R18C25 Rupture and Justification for Return to Power.
3..
McGuire Nuclear Power Station Unit 2 Evaluation of B&W Alloy 600 Plugs Presentation Material.
.4.
McGuire Nuclear Station - Unit 2 Evaluation of B&W Alloy 600 Plugs Justiff. cation for Return to Power B&W Document Identifier 51-1175791-00.
The above material was discussed with flRC representatives during ar. August 31, 1989 meeting in White Flint, MD. This meeting was held to inform the NRC of
.our findings from the inspection of the Unit 2 steam generator tubes and plugs during the current refueling outage. The meeting also fulfilled a prior conmiitment made in my letter dated May 8,1989.
Babcock & Wilcox considers Items 3 and 4 identified above to be proprietary.
The proprietary determination was discussed by B&W in a letter and affidavit to the NRC dated September 6, 1989. This letter was signed by Mr. J. H.
+
Taylor, Manager of B&W Licensing Services and is attached herein.
Also attached to this letter is a revised Page 7-7 of the document entitled, McGuire Unit 1 Nuclear Power Station Evaluation of Degradation of Tube R18C25 and Justification for Return to Power. This document was submitted as an attachment to my May 8, 1989 letter. This revision corrects two errors in the chemistry parameters contained in Table 7-3.
These errors were found during a recent review of this document and we do not feel they are technically APol Y# FCC
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. margin.
I hereby reaffirm my previous comitment to perform 100% bobbin coil eddy current inspection of the McGuire Unit I steam generators as stated in my May 8, 1989 letter. This will be done during the next refueling outage, currently projected for March 1990. We will comunicate the results of the inspection to the NRC staff in a report prior to restart from the refueling outage.
Based upon NRC staff comments at the August 31, 1989 meeting, we now under-stand that a meeting to present the inspection report and discuss the findings and conclusions will not be required. With this understanding, we will cancel the comitment to hold this meeting I made in my May 8,1989 letter.
I appreciate the NRC staff's effort and timely action in support of McGuire.
Please let me, or the appropriate member of my staff, know of any further concerns you may have regarding this matter.
Very Truly Yours, bY t
Hal B'. Tucker (With Attachments) xc: Mr. S. D. Ebneter Mr. J. H. Taylor Regional Administrator, RII Babcock & Wilcox U.S. Nuclear Regulatory Comission P.O. Box 10935 101 Marietta Street, NW, Suite 2900 Lynchburg, VA 24506-0935 Atlanta, Georgia 30323 Mr. P. K. VanDoorn NRC Resident Inspector McGuire Nuclear Station Mr. Darl Hood Office of Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission Washington, D.C.
20555
a TABLE 7-3 l
MCGUIRE UNIT 1 SECONDARY CHEMISTRY EXCURSIONS FOR THE SUBJECT REVIEW PERIOD (1986-1989) (1)
Minor Chemistry Excursions (Action Level 1)
Date Parameter Max. Value Duration Cause 04/16/86 Sulfate 37 ppb 5.0 hrs Startup 09/14/86 Cat. Cond.
1.0 umhos 5.5 hrs Startup 09/26/86 Sulfa.te 28 ppb 4.7 hrs Startup 11/16/87 Cat. Cond.
1.2 umhos 1.3 hrs Startup 11/17/87 Chloride 21 ppb 1.2 hrs Startup 11/20/87 Sulfate 21 ppb 1.6 hrs Startup 11/20/87 Sodium 25 ppb 2.3 hrs Startup 01/20/88 Chloride 22 ppb 3.7 hrs Polishers (2) 06/21/88 Sodium 30 ppb 3.2 hrs Startup 07/04/88 Sulfate 21 ppb 2.2 hrs Load Follow 08/25/88 Sodium 23 ppb 3.5 hrs YM Contamination (3)
Moderate Chemistry Excursions (Action Level 2)
Date Parameter Max. Value Duration Cause 09/16/86 Cat. Cond.
5.3 umhos 15.2 hrs Condenser Leak 09/16/86 Sodium 480 ppb 8.0 hrs Condenser Leak 09/16/86 Sulfate 202 ppb 23.3 hrs Condenser Leak 09/16/86 Chloride
>20 ppb 8.0 hrs Condenser Leak 02/17/87 Sodium 245 ppb 12.0 hrs YH Hx Tube Leak (4) 02/02/88 Sodium 125 ppb 24.2 hrs YH Hx Tube Leak (4)
Severe Chemistry Excursions (Action Level 3)
NONE Notes:
(1) Pertinent steam generator chemistry parameters per the EPRI i
Secondary Chemistry Guidelines for Mode 1 operation.
(2) Leachable chloride from powdered resin upon valving condensate polisher vessel in service.
(3) Filtered water ingress into demineralized water (YM) header.
(4) Plant heating converter (YH) tube leak resulting in contamination of condensate storage tank with sodium nitrite corrosion inhibitor.
l 7-7 Rev. 1 9/19/89 L__.,___4__.-
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