ML20062J415
| ML20062J415 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/02/1982 |
| From: | Mardis D FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820 3F-0882-04, IEB-82-02, NUDOCS 8208160360 | |
| Download: ML20062J415 (5) | |
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< 6. il l Florida Power C O a P o e a f a o es August 2,1982
- 3F-0832-04 File: 3-0-3-a-3 Mr. 3. P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 Atlanta, G A 30303
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 IE Bulletin No. 32-02 Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary in PWR Plants
Dear Mr. O'Reilly:
l IE Bulletin No. 82-02 was issued, by letter dated June 2,1982, to notify us about incidents of severe degradation in threaded fasteners in closures in the reactor coolant pressure boundary (RCPB) and to request appropriate actions. Item 5 of your letter requested submittal of a report detailing the results of the reviews requested in Item 3.
Florida Power Corporation hereby provides the following response under oath or affirmation pursuant to Section IS2a, Atomic Energy Act of 1954, as amended.
Item 3a NRC Information Notice Nos. 30-27 and 82-06, and similar Institute of Nuclear Power Operations (INPO) correspondence (with recommendations) have been issued in regard to corrosion problems associated with bolts / studs in RCPB closures (INPO/NSAC SER 81-12). To assist the Nuclear Regulatory Commission in its ongoing review and assessment of the scope of the problem you are asked to provide the following information for closures and connections within the scope of this bulletin:
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.
1 8208160360 820802 DR ADOCK 05000 g
General Office 32o1 Tnirty-fourin street soutn. P O Box 14042, st Petersburg. Flonda 33733 e 813-866-5151
Mr. 3. P. O'Reilly, Regional Administrator U.S. Nuclear Regulatory Commission August 2,1982 Page 2
Response
1.
Steam Generators (SG) - Lower manways have exhibited minor leakage during past outages. During the 1980 Refueling Outage, SG 'B' lower manway was removed, cleaned and a new gasket was installed. Also, due to failures of these studs at other B&W plants, an augmented inspection program was put into effect. During every refueling outage, the studs on the upper and lower manways are ultrasonicly examined in place. When a manway is removed for any reason, the studs receive magnetic particle and ultrasonic examinations in the removed condition. No abnormal indications have been found to date.
2.
Reactor Coolant Pump - A visual inspection was performed on July 10,1980, in response to experiences at Fort Calhoun. No degradation was observed.
Normal ultrasonic inservice inspections have not revealed any problems.
3.
Valves -
1)
CFV-3 had a bonnet leak in 1979 which was repaired by bonnet removal, cleaning, gasket replacement, and retorquing.
11)
CFV-1 presently has a minor leak at the hinge pin area. This valve will be repaired during the next refueling outage. No studs have been replaced due to degradation or failure.
4.
Control Rod Drive Mechanism (CRDM) - All 96 CRDMs were removed during the 1980 Refueling Outage due to excessive leakage.
The flanges were cleaned, inspected, repaired (where necessary), and new gaskets were installed and torqued.
During the 1981 Refueling Outage, several flanges were again noted as leaking and were repaired and retorqued. An Engineering Task Force has been assigned to review the problem.
Details of this effort will be provided in the second report due to the nature of ongoing activities.
Included in the analysis are locations included in the scope of this Bulletin but were found not to be leaking. These are:
1.
Pressurizer - The pressurizer manway has not been removed since plant startup and has shown no signs of leskage. The heater bundle flange was seal welded in 1979 and has shown no signs of leakage.
2.
Reactor Vessel - The studs have been inspected using inservice inspection procedures which have incorporated Regulatory Guide 1.65 guidance. No leakage has been observed in this area to date.
These inspections are not strictly limited to the last outage.
Several inspections were performed during the 1980 Refueling Outage.
Mr. 3. P. O'Ellly, Regional Administrator U.S. Nuclear Regulatory Commission August 2,1982 Page 3 Item 3b Identify those closures and connections, if any, where fastener lubricants and injection sealant materials have been or are being used and report on plant experience with their application particularly any instances of stress corrosion cracking (SCC) of fasteners. Include types and composition of materials used.
Response
Please see Table 1 (attached) for a list of lubricants used and the location.
No injection sealant materials have been used in the reactor coolant pressure boundary that fall within the scope of this Bulletin.
The costs (manpower and radiation exposure) associated with this Bulletin are being collected separately per your request and will be included in future correspondence.
Estimated manpower costs are 1,500 man-hours (Engineering and Technicians).
Very truly yours, DJ ada David G. Mardis Acting Manager Nuclear Licensing Attachment MAF:cmd cc:
Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555
TABLE 1 COMPONENT LOCATION MATERIAL LUBRICANT OTSG PRIMARY SA-320 MOLYKOTE MANWAY L-43 G
OTSG PRIMARY SA-320 MOLYKOTE HANDHOLE L-43 G
PRESSURIZER HEATER BUNDLE SA-320 MOLYKOTE L-43 G
PRESSURIZER MANWAY SA-320 MOLYKOTE L-43 G
REACTOR CLOSURE SA-540 MOLYKOTE VESSEL STUDS B-23 G
CRDM HOLDDOWN SA-453 NEOLUBE BOLTS 660-A
& FEL PRO-N1000 RC PUMP MOTOR STAND SA-540 DAG 156
& MTR.
B23 & 24 NEOLUBE FEL PRO-C5A i
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STATE OF FLORIDA COUNTY OF PINELLAS D.
G.
Mardis states that he is the Acting Manager, Nuclear Licensing, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.
F AL
'~~~D. G. Mirdls.
Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 2nd day of August,1982.
g Notfly Public Notary Public, State of Florida at Large, My Commission Expires: May 29,1984 1
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