ML20070A995

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Forwards Response to IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants, Item 1 for Unit 1 & Items 2 & 4 for Unit 3.Response to Items 2 & 4 for Units 1 & 2 Will Be Provided Following Next Refueling Outage
ML20070A995
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 11/15/1982
From: Tucker H
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8212090420
Download: ML20070A995 (4)


Text

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e Duxe:Pakis COMPANY 18.0." box 33180 CIIARLOTTE, N.O. 28242 II AL II. TIJCKER TELEPHONE no amsa e7Nb'v% 1 6 O,e* 19k!o

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Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Subject:

Oconee Nuclear Station Docket Nos. 50-269, -270, -287

Dear Sir:

In response to IE Bulletin 82-02 dated June 2, 1982, please find attached responses to Items 1 (covering all Oconee units). 2 and 4 (Unit 3 only).

Duke Power provided a response to Items 3 and 5 in our submittal dated July 29, 1982. Responses to Items 2 and 4 for Units 1 and 2 will be provided following the next refueling outage of each unit as specified in the Bulletin.

I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge, executed on November 15, 1982.

Very truly yours, W

cc:

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Hal B. Tucker l

JFN/php Attachment cc:

Mr. W. T. Orders NRC Resident Inspector Oconee Nuclear Station Mr. Philip C. Wagner Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 8212090420 921115 PDR ADOCK 05000269 G

PDR IEst

Item 1 Where procedures do not exist, develop and implement maintenance procedures i

for threaded fastener practices. These procedures should include, but not be limited to the following: (1) maintenance crew training of proper bolting /

stud practices, tools application, specifications and requirements, (2) deten-sioning and retensioning practices (torque iteration), specified tolerances, and other controls for disassembly and reassembly of component closure / seal connections, (3) gasket installation and controls, and (4) retensioning methods and other measurea to eliminate reactor coolant leakage during operations.

Quality assurance measures should also be established for proper selection, procurement, and application of fastener lubricants and injection sealant compounds to minimize fastener susceptibility to SCC environments.

Response

It has always been the philosophy of Mechanical Maintenance that when a pro-cedure for any component is developed where that component has bolting or threaded fasteners, that the procedure will require certain steps to be followed to ensure that the bolting or threaded fasteners are properly maintained..This includes the special considerations as requested in the bulletin regarding subitems (2), (3), and (4) of Item 1.

The Technical Training Center covers as a part of its ongoing Basic Mechanical Maintenance Training Program topics which include Fasteners, use of hydraulic torque wrenches, and Metrology which covers use of torque wrenches. This existing training program satisfies the requirements of subitem 1 of Item 1.

Item 2 Threaded fasteners of closure connections, identified in the scope of this bulletin, when opened for compor.ent inspection or maintenance shall be removed *,

cleaned, and inspected per IWA-2210 and IWA-2220 of ASME Code'Section XI (1974 edition or later) before being reused.

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Response

The components that were inspected during Unit 3's latest refueling outage included the following:

1) OTSG upper and lower manway bolting on both A and B OTSGs.

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2) Pressurizer Heater Bundle bolting.
3) Pressurizer Manway bolting.
4) RCP seal housing bolting on RCPs 3Al and 3A2.
5) RCP main flange bolting on all four RCPs.
6) 4 CRDMs.

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O Item 4 A written report signed under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954 as amended, shall be submitted to the Regional Administrator of the appropriate NRC Regional Office within 60 days following the completion of the outage during which Action Item 2 was performed. The report is to include:

a.

A statement that Action Item 1 has been completed.

b.

Identification of the specific connections examined as required by Action Item 2.

c.

The results of the examinations performed on the threaded fasteners as required by Action Item 2.

If no degradation was observed for a particular connection, a statement to that effect, identification of the connection and, whether the fasteners were examined in place or removed is all that is required. If degradation was observed, the report should provide detailed information.

Response

Sub-item a As was discussed above in Item 1, the procedures as discussed in the bulletin have been completed and these along with a training program are on file.

Sub-item b Same as was listed in Item 2.

Sub-item e The method and results of the examination of the components listed in Item 2 as follows:

Component Inspection Method Inspection Results 1.

OTSG "A" Upper UT, MT, Hardness No reportable or rejectable Manway Bolting indications found.

2.

OTSG "A" Lower UT, MT, Hardness Studs numbers 1 and 11 were Manway Bolting rejected due to unacceptable hardness, no other repor' table or rejectable indications found.

3.

OTSG "B" Upper UT, MT, Hardness No reportable or rejectable Manway Bolting indications found.

4.

OTSG "B" Lower UT, MT, Hardness No reportable or rejectable Manway Bolti4g indications found.

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Pressurizer l'inway UT of Studs, Visual of No reportable or rejectable nuts (in place) indications found.

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6.

Pressurizer Heater UT of Studs, Visual of' No reportable or rejectable Bundles nuts (in place) indicationc found.

7.

RCP Seal Housing Bolts MT, UT, Visual (Base-Bolting replaced with new on RCPs 3Al and 3A2 line) material due to seal modifi-cation.

8.

RCP Main Flange Visual Dimensional, Two studs on RCP 3Al and Bolting, all four RCPs UT (in place); UT, MT, three studs on RCP 3A2 were and visual (baseline) replaced due to corrosion /

on new studs erosion vastage. Smallest diameter was 2.997 inches, was 3.846 originally. No reportable or rejectable ~

indications on remaining bolting.

9.

CRDMs Visual (baseline) on Bolting were replaced with new new bolting material due to severe galling of old bolting during removal of CRDMs.

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