ML20062H094
| ML20062H094 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/02/1982 |
| From: | Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8208130296 | |
| Download: ML20062H094 (4) | |
Text
- ~'*
John D. @fToole VtCe Prevdent Consohdated Edison Company of New York, Inc.
4 Irving Place. New York, NY 10003 Telephone (212) 46r>2533 August 2, 1982 Re Indian Point Unit No. 2 Docket No. 50-247 Mr. Ronald C. Haynes, Regional Administrator Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406
Dear Mr. Haynes:
Our response to Action Item 3a of IE Bulletin No. 82-02, " Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Platits" concerning information compiled during the last refueling outage is provided in Attachment A to this letter.
The information r.ecessary to respond to the remainder of action item 3a and Action Item 3b of the subject bulletin is currently being compiled and we presently expect to submit it by August 30, 1982.
Our response is being provided pursuant to Section 182 of the Atomic Energy Act as amended.
Should you or your staff have any questions, please contact us.
Very truly yours,
/
,s [ z, v v1' Subscribed and sworn to before me this o'2, day of August, 1982.
/
- >J-Nutary Public DAVID WATSON tuotary Public Sta*e of New York rio. 03 4004876 Quallined in Bronx County Commission f.xpires March 30,1983 attach.
cc:
Mr. T. Rebelowski, Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511 8208130296 820802 l
PDR ADOCK 05000247 (l
G PDR
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ATTACHMENT A i
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Response to Action Item 3a of IE Bulletin No. 82-02
" Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants" 4
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l Consolidated Edi,7on Company of New York, Inc.
Indian Point Unit No. 2 L
Docket No. 50-247 August, 1982 l
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Action Item #3a (IE Bulletin No. 82-02):
Identify those bolted closures of the RCPB that have experienced leakage, particularly those locations where leakage occurred during the most recent plant operating cycle. Describe the inspections made and corrective measures taken to eliminate the problem.
If the leakage was attributed to gasket failure or its design, so indicate.
Response
The following bolted closures of the RCPB have evidenced build-up of boric acid crystals as identified during inservice inspections performed during the most recent (fourth). refueling outage and the indicated corrective actions have been taken:
A.
Reactor Coolant Pump 23 - A leak was observed in the pump main fla nge. The insulation facilitated a build-up of boric acid.
Eight of 24 studs experienced wastage at the stud / bowl interf ace.
Sixteen of 24 exhibited some surface corrosion or rust. All 24 studs and the associated gasket were replaced.
Additionally, the blanket insulation was changed to a preformed metal type to preclude potentici future build-up.
B.
Steam Generators - Steam generator manways have leaked in the past, but no leaks were identified just prior to the 1981 refueling outage. Bolting on the eight manway covers from four steam generators was removed and inspected by UT, VT, and MT methods. Of the 128 bolts inspected, 7 were rejected and replaced as follows:
Steam Hot / Cold Generator Leg Inspection Finding
- Bolts 22 H
MT 1" longi-1 tudinal crack 22 C
VT Thread Defor-1 mation 22 C
UT Crack 1
22 C
UT Crack 1
23 C
VT Damage, tool 1
marks 24 C
MT Crack 1
24 C
UT Crack 1
It should be noted that these bolts are 1.875" diameter and required only visual inspection per ASME XI; therefore, these was no baseline surface or volumetric data for comparison.
C.
Pressurizer bolts - A leak was observed in the manway. The hs lting was removed and examined visually with no indications. A repl.seement gasket was inta11ed to correct the leak.
D.
Valve 895 D, Safety Injection 10" check - The carbon steel cover exhibited some corrosion from a previous leak. All the studs were replaced. The removed studs were inspected and had no evidence of corrosion.
The cover is scheduled for replacement at the upcoming 1982. Refueling Outage.
E.
Valve 838 D, Safety Injection 6" check - Two of the eight studs were corroded. The attack was localized next to the valve body.
There was no indication of a problem with other studs. All the studs were replaced.
.s