ML20072F772
| ML20072F772 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/08/1983 |
| From: | Otoole R 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 8303240418 | |
| Download: ML20072F772 (7) | |
Text
_
.e John D. O'Toola Vice President Conschdated Edison Company of New York, Inc 4 Irving Place, New York, NY 10003 Telephone (212) 460-2533 March 8, 1983 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 :
" Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of IWR Plants." requested information regarding inspection of threaded fasteners in the reactor coolant boundary.
Con Edison has established an ongoing program for inspection of threaded fasteners in systems containing borated water including those within the scope of Bulletin 82-02.
It is intended to continue this inspection program through the next refueling outage.
Attachment A to this letter contains our response to Action Item 4 of IE Bulletin No. 82-02, This information completes our response to the subject bulletin.
Information requested in support of Action Item 3 has been previously provided by letters dated August 2,
1982 and August 31, 1982.
Our response is being provided pursuant to Section 182 of the Atomic Energy Act as amended.
Should you or your staff have any additional questions, please contact us.
Ve truly ourji, lLlW.
,y
,V
/gornto Subscr bed and 8/ day befor.,de this sch,19{.'
of
/
/-
'U_
'i v u.th ( m.
Notary PubM c-THOMAS LOVE Notary Public Stra of New York No. 31-2WWa Quellffed in New York Cnnty l
Commission Expires March R.19d 3 I
8303240418 830308 PDR ADOCK 05000247 Q
_2-attach.
cc:
Mr. Thomas Foley, Senior Resident Inspector U. S. Nuclear Regulatory Commission P.
O.
Box 38 Buchanan, New York 10511 4
e o
ATTACliMENT A Response to Action Item 4 of IE Bulletin No. 82-02
" Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants" Consolidated Edison Company of New York, Inc.
Indian Point Unit No. 2 Docket No. 50-247 March, 1983
b Action Item 4: A written _ report signed under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954 as amendoJ, 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:
Action Item 4a A statement that Action Item 1 has been completed.
l Action Item 1 Where procedures do not exist, develop and implement maintenance procedures for threaded fastener practices.
These procedures should include, but not limited to the following:
(1) maintenance crew training of proper bolting / stud practices,. tools application, specifications and requirements, (2) detensioning-and retensioning practicos (torque iteration), specified tolerences, and other controls for disassembly and reassembly of component closure / seal connections, (3) gasket installation and controls, and (4) retensioning methods and other measures 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 susceptability to SCC environments.
Response to Action Item 4a.
l
.A.
Con Edision is presently in the process of establishing a training program for maintenance mechanics which will encompass:
proper bolting and stud practices, tool application, specifications and requirements.
B.
Individual generic procedures do not separately cover practices described in question 1, sections (2) and (3).
However, each of these practices is covered in detail in the specific procedures for threaded fasteners in closures in the reactor coolant i
boundary.
C.
Retensioning methods and other measures to eliminate reactor coolant leakage during operations are covered by specific work step list or procedures developed as required by circumstances.
D.
The selection and application of fastener lubricants for use at Indian Point station is covered by Engineering specification.
At the present time the only injection sealant approved for use at Indian Point is Furmanite which is also covered by Pngineering specification.
Procurement of these materials for use in connections within the scope of this bulletin is appropriately controlled in accordance with the Indian Point Unit No. 2 Quality Assurance program requirements.
,e
,a 7.n-.. _,., _ -
,g.
~ _ _
Action Item 4.b.
Identification of the specific connections examined as required by Action Item 2.
Action Item 2 3
Threaded fasteners of-closure connections, identified in the scope of this bulletin, when opened for component inspection or maintenance shall be removed *, cleaned, and inspected per IWA-2210 and IWA-222 of ASME Code Section XI (1974 edition or later) before being reused.
i
- Fasteners " seized" or designed with interference fit, may be inspected in place.
f Response to Action Item 4.b.
1 I
Tables A and B. (attached) identify the specific connections examined in response to Action Item 2.
Action Item 4.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, 4
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 to Acti">n Item 4.c.
Connections examined in response to Action Item 2 which exhibited no-degradation are identified in Table A.
Connections examined in response to Action Item 2 which exhibited fastener degradation are detailed in Table B.
k b
i L
i i
1 i
,._["E'_..-.
.,____,_,7
TABLE A-FASTENERS WITH NO DEGRADATION 1992 REFUELING OUTAGE FASTENER INSPECTION PROGRAM REQUIRED BY NRC IE BULLETIN NO. 82-02 FASTENERS FOR EXAM'D INSPECTION
,CMPO"ENT CONNECTION COMPONENT IN-PLACE REMOVED VT MT UT REMARXS
'eactor vessel Head to flange 54 Studs X
X X
.X 1*
- /G-21 Frimary Manways 32 Bolts X
X X.
- /G-23 Primary Manways 32 Bolts X
X X
- /G-24 Primary Manways 32 Bolts X
X X Talve 730 Bonnet to body 16 Studs X
X 2*
'alve 839A Donnet to body 12 Studs X
X X 3*
"enarks
'l.
Five of fifty-four washers exhibited some pitting or corrosion which was evaluated by Engineering and found acceptable as is.
'2.
Valve 730, 14" gate, second isolation valve from loop twenty two to the suction of the FHR pumps was examined in the asseabled condition and did not exhibit any fastener degradation to the exposed portions of the studs or nuts.
Although this valve was not disassembled, it is identified herein because it was inspected as a follow-up to valve 731, see Table B.
'3.
Valve 838A, G"
check on the Safety Injection System ( RIIR return), was opened for internal inspection.
The studs, however, could not be removed as they were " seized" in the body.
The exposed portion of the studs were examined by VT and MT methods to-the extent possible and the main bonnet gasket was replaced upon reassembly of the valve after internal inspections were performed.
E 6
6
TABLE B-FASTENERS SHOWING DEGRADATION 1982 FEFUELING OUTAGE FASTENER INSPECTION PROGRNi REOUIRED BY NRC IE BULLETIN No. 82-02 FASTENERS FOR EXAM'D INSPECTION 2:!PONENT CONNECTION COMPONENTS IN-PLACE REMOVED VT MT UT REMARKS
/G-22 Primary Manway 32 Bolts X
X X 1*
11ve 731 Bonnet to body 16 Studs X
X 2*
21ve 397A Eonnet to body 16 Studs X
X 3*
31ve 3979 Bonnet to body 16 Studs X
X 3*
anarks:
1.
Stean Generator #22:
Five of thirty-two bolts on S/G #22 experienced degradation since the last Refueling Outage (April, 1981).
One init on the hot-leg manway was rejected for a three inch linear indication with no measureable width.
Four bolts on the cold leg manway were rejected for thread corrosion.
The damaged bolts were clustered (positions #9,10,12&l5) and the surrounding insulation indicated the presence of a leak.
The maintenance procedures for the reinstallation of these manways included the cleaning and inspection of all bolts, bolt holes, closure surfaces and the installation of new gaskets to correct the leakage problem.
The five damaged bolts were replaced.
2.
Valve 731, 14" gate, first isolation valve from loop twenty two to the suction of the RHR pumps exhibited corrosion to bonnet bolting detected upon removal of boron deposits resulting from a packing leak.
All of the 1 3/4" diameter bolts exhibited corrosion with the worst cases (approximately 6) being reduced to approximately 1"
in diameter.
All bolts were replaced and the packing was repaired.
3.
Valve 897A & 897D, 10" check valves on the RHR system, exhibited corrosion to the roots of the threads.
The studs were replaced and new gaskets were installed.
e 8