ML17053B505
| ML17053B505 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 03/14/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Rhode G NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8003260045 | |
| Download: ML17053B505 (10) | |
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Docket No. 50-410 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406 March 14, 1980 Niagara'Mohawk Power Corporation ATTN:
Mr.
G.
K.
Rhode Vice President System Project Management 300 Erie Boulevard, West
- Syracuse, New York 13202 Gentlemen:
The enclosed IE Circular No. 80"04, "Securing of Threaded Locking Devices on Safety-Related Equipment," is forwarded to you for information.
No written response is required.'f you desire additional information regarding this
- matter, please contact this office.
Sincerely, Boyce H. Grier
- Director,
Enclosures:
1.
IE Circular No. 80-04 2.
List of Recently Issued IE Circulars CONTA.CT:
L.
E. Tripp (215-337-5282) cc w/encls:
Eugene B. Thomas, Jr.,
Esquire
ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
. WASHINGTON, D. C.
20555 SSINS NO.
6830 Accession No.:
7912190662 IE Circular No. 80-04 Date:
March 14, 1980 Page 1 of 3
.SECURING OF THREADED LOCKING DEVICES ON SAFETY-RELATED EQUIPMENT Description of Circumstances:
In recent months, several licensee event reports have been submitted that address the inoperability of safety-related equipment caused by loosened threaded locking devices.
Some of the events are listed below:
I.
MAIN STEAM CHECK VALVE HEX NUT LOCKING DEVICES, TURKEY POINT NO.
3 REPORTABLE OCCURRENCE 250"79-31 (Oct.
22, 1979)
During a planned outage of Turkey Point Unit No.
3 on October 7, 1979, a
two-inch internal diameter hex nut was discovered in the internals of a steam supply valve for a moisture separator-reheater.
Investigation revealed that the nut was missing from the disc stud of the 3A main steam check valve.
The disc and disc stud were in the proper. position and the valve was fully operable.
The 3B and 3C main steam check valves were inspected and the disc stud, nut and locking washer were in place although some distress was noted on the 3C locking washer in that the tack welds on the locking pin had separated.
The licensee installed an improved locking device on the disc stud on each of the three main steam check valves.
The locking device consists of a tab washer that is prevented from rotating by a pin -and by fingers that extended on either side of'he valve arm; the tabs are bent up against two faces of the hex nut.
The main steam isolation valves (MSIV) have the same type of hex nut locking device.
The valves are Schutte and Koerting SK Type 828.
II.
=SLIPPAGE AND MISALIGNMENT OF VALVE LINKAGES, DAVIS-BESSE LICENSEE EVENT REPORT NOS78-101 (Nov. 1, 1978),78-126 (Jan.
26, 1979),79-068 (July 19, 1979),
and 79-098 (Oct. 30, 1979)
These reports involve the inoperability of 'two service water system valves and one component cooling water system valve.
The valves were declared inoperable because the nut on the actuator linkage was either missing or had loosened to the point where there was slippage and misalign-ment of the valve linkage.
These valves were provided'y Hammel-Dahl.
The supplier has provided the licensee with an addendum to the instruction manual that defines the torque requirements for the cap screw that is used to retain the actuator link arm to the valve disc arm.
Enclosure 1
IE Circular No. 80-04 Date:
March 14, 1980 Page 2 of 3'II.
ECCS SUBSYSTEM INOPERABLE - NO.
12 SAFETY INJECTION PUMP IMPELLER LOCKNUTS
- LOOSE, SALEM NO.
1 LICENSEE EVENT REPORT NO. 79-68 (Dec.
20, 1979).
The AC supply breaker tripped when No; 12 Safety Injection (SI)
Pump was
- started, to fill the accumulators on October 18, 1979.
When the rotor could not be turned by hand, the upper casing was removed for an inspec-tion of the pump internals.
The radial and thrust locknuts were found loosened to the extent that they could be removed by hand.
The impeller spacer sleeves were worn and the impeller shaft was slightly bent.
The pump was reworked, tested and returned to service on November 2, 1979.
The locknuts on the three other Unit 1 and Unit 2 Safety Injection (SI)
Pumps were inspected and two pump impeller locknuts were found loose, and one pump impeller locknut was found secured with setscrews that had been installed by mistake at the manufacturing facility and the impeller was sent back to the manufacturer for rework.
The locknuts on all of the SI pumps were secured using Locktite compound per Public Service Engineering Department recommendation and the pump manufacturer's concurrence.
The pumps are horizontal, centrifugal, ten stage units manufactured by Pacific
- Pumps, Inc.
IV.
TARGET ROCK MOTOR OPERATED GLOBE VALVES - BUSHING NOT STAKED, ANO.NO.
2 LICENSEE EVENT REPORT 79"93 (FEB. 14, 1980)
While investigating the failure of a High Pressure Safety Injection (HPSI) header shut-off valve at Arkansas Nuclear One, Unit 2, the threaded bushing was found loose.
The bushing was not staked or otherwise secured to prevent movement.
This bushing is part of the mechanism which converts the valve stem rotation to linear travel of the disk.
The full open limit switch is gear driven by the valve operator and movement of the bushing can alter the relationship between stem rotation and linear travel such that valve travel in the open direction may be terminated prematurely by the limit switch.
The HPSI header shut-off valves at ANO-2 are Target R'ock 2-inch 1500¹ ANSI Motor Operated Globe Valves.
Arkansas Power 8 Light found that a similar problem exists with the Low Pressure Safety Injection (LPSI) header shut"off valves which are Target Rock 6-inch 1500¹ ANSI Motor'Operated Globe Valves.
Target Rock has provided Arkansas Power 8 Light Company with a procedure for staking the bushing nuts.
V.
OTHER EVENTS Loose locking devices were also identified in one of the I 8 E Bulletins and two of the I 8 E Circulars issued in 1979:
IE Circular 79-04 Loose Locking Nut on Limitorque Valve Operators, IE Circular 79-19 Loose Locking Devices on Ingersoll-Rand
- Pumps, IE Bulletin 79-15 Deep Draft Pumps.
~~
Enclosure j.
Recommended Action for Licensees Consideration:
IE Circular No. 80-04 Date:
March 14, 1980 Page 3 of 3 It is recommended that licensees of operating power reactors and holders of construction permits review the specific items presented in the "Description of Circumstances" for applicability at their facilities and review their installation and maintenance procedures to determine that whether securing of locking devices has been addressed in these procedures.
It is further recommended that installation and maintenance procedures for all safety-related components be.reviewed to be sure the securing of locking devices is adequately covered.
No written response to this Circular is required.
If you require additional information regarding these matters, contact the Director of the appropriate NRC Regional Office.
ENCLOSURE 2 IE Circular No. 80-04 Date:
March 14, 1980 Page 1 of 1 RECENTLY ISSUED IE CIRCULARS Circular No.
79-18 Subject Proper-Installation of Target Rock Safety-Relief Yalves First Date of Issue 9/10/79 Issued To All Power Reactor Licensees with an Operating License (OL) or Construction Permit (CP) 79-19 79"20 79-21 79"22 79-23 79"24 Loose Locking Devices 9/13/79 on Ingersoll-Rand Pumps Failure of GTE Sylvania 9/24/79
- Relay, Type PM Bulletin
- 7305, Catalog 5U12-11-AC with a 120V AC Coil Prevention of Unplanned 10/19/79 Releases of Radioactivity Stroke Times for Power ll/16/79 Operated Relief Yalves Motor Starters and Con-ll/26/79 tactors Failed to Op-erate Proper Installation and 'll/26/79
, Calibration of Core Spray Pipe Break Detection Equipment on BMRs All Power Reactor Licensees with an OL or CP All Power Reactor Licensees with an OL or CP All Power Reactor Licensees with an OL or CP All Power Reactor Licensees with an OL or CP All Power Reactor Licensees with an OL or CP All Power Reactor Facilities with an OL or CP 80-01 80-02 80-03 Service Advice for GE Induction Disc Relays Nuclear Power Plant Staff Mork Hours Protection from Toxic Gas Hazards 1/17/80 2/1/80 3/6/80 All Power Reactor Faci-lities with an OL or CP All Power and Research Reactors with an OL or CP All Power Reactor Facil-ities with an OL