ML19345C920
| ML19345C920 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/10/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Jones OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8012080618 | |
| Download: ML19345C920 (1) | |
Text
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,.e uNiTso STATES POR:HQ NUCLEAR REGULATORY COMMISSION LPOR
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ill RYAN 7t.AZA ORIVE. SulTE 10C0
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Novemoer 10, 1980 m
Docket No.
50-235-e;_.
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Cmaha Puolic Pcwer Distric:
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ATTN:
W. C. Jones, Division Manager -
g Production Ocerations Q*
o 1523 Harney Stree:
Omaha, Nacraska 58102 Gentlemen:
l l~nis IE Information Notice is providec as an early notification of a possibly significan :nattar.
It is ex:ected. hat recipients will review tne information i
for possible acplicability to neir facility. No specific action or res;:ense is recuestad a: :nis time.
If fur.m ' NRC evaluations so inoicate, an IE Circular or Sulletin will be issued to rec:mmenc Or recuest s:ecific licensee actions.
If you have cuestions regarding :nis matter, clease contac ne Direct:r of the accrecriate NRC Regional Office.
j Sincerely,
.l.
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J. g. t / j ' w / {.. l
~
s Karl V. Seyfri
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Director
/
1
Enclosures:
-1.
IE Infomation Notice No. 30 41 2.
List of Recently Issued IE Infomation l
Notices l
cc:
- 5. C. Stevens, Manager l
l Por Calhoun Station Pos: Office Sox 98 For: Calhoun, Nebraska 58102 8012080 h
G/f
SSINS No.:
6835 Accession No.:
8008220250 UNITED STATES NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT (s )
WASHINGTON, D.C.
20555
(_ /'
IE Information Notice No. 80-41 Date:
Novemoer 10, 1980 Page 1 of 1 FAILURE OF SkING CHECX VALVE IN THE DECAY HEAT REMOVAL SYSTEM AT DAVIS-SESSE UNIT NO. 1 Descriotion of Circumstances:
On October 9, 1986 the Resident Reactor Inspector at the Davis-Besse facility was informed that the licensee had performed leak rate tests and identified exces-sive leakage through Decay Heat Removal System check valve CF-30.
Valve CF-30 is the incoard one of two in-series check valves that is used to isolate the reactor coolant system from the low pressure decay heat remov'al system.
On further-investigation the licensee found that the valve disc and arm had separated from the valve body and was lodged just under the valve cover plate.
The two 2 5/8 x 5/8. inch bolts and locking mecnanism for the bolts that holds the arm to the valve body were mi.= sing and have not oeen located.
The CF-30 valve is a 14-inch swing check salve manufactured by Velan Valve Corporation.
The cause of the failure has not been identified.
The test that was in progress when the failure was identified was being con-ducted in response to a letter from Darrell G. Eisenhut, Office of Nuclear Reactor Regulations to all Light Water Reactor Licensees, LWR Paimary Coolant System Pressure Isolation Valves, February 23, 1980.
This IE Information Notice is provided as an early notification of a possibly significant matter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or _ response is requested at this time.
If NRC evaluations _so indicate, further licensee actions may be requested or required.
No written response to this IE Information Notice is required.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
f IE Information Notice No. 80-41 Novemoer 10, 1980 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To
' Notice No.
Iss: sed 30-3^
Boron Dilution of Reactor 9/26/80 All Pressurized Coolant During Steam Water Reactor Generator Decontamination Facilities holding 4
cower reactor Operating Licenses (OLs) 80-35 Leaking and Dislodged 10/10/80 All categories G and Iccine-124 Implant Seeds G1 medical licensees 80-36 Failure of Steam 10/10/80 All nuclear power Generator Suoport Bolting reactor facilities holding Ooerating Licensees (OLs) or Construction Permits (cps) 80-37 Containment Cooler Leaks.
10/24/80 All nuclear power and Reactor Cavity far lities holding Flooding at Indian Point power reactor Operating Unit 2 Licenses (OLs) or Construction Permits (cps) 80-38 Cracking in-Charging 10/30/80 All Pressurized Water Pumo Casing Cladding Reactor Facilities holding power reactor Operating Licenses (OLs) anu Constmiction Permits (cps) 80-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor Operating Licenses (OLs) or Construc-tion Permits (cps) 80-40 Excessive Nitrogen 11/7/80 All power facilities Supply Pressure with an Coerating License Actuates Safety-Relief (OL) or Construction Valve Operation to Permit (CP)
Cause Reactor Depressuriza-tion Enclosure
.