ML18081B094

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Forwards IE Info Notice 80-03, Main Turbine Electrohydraulic Control Sys. No Specific Action Required
ML18081B094
Person / Time
Site: Salem, Hope Creek  
Issue date: 01/31/1980
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Martin T
Public Service Enterprise Group
References
NUDOCS 8002250141
Download: ML18081B094 (3)


Text

UNITED ST ATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket Nos. 50-354 50-355 50-311 Public Service Electric & Gas Company ATTN:

Mr. T. J. Martin Vice President Engineering and Construction 80 Park Place Newark, New Jersey 07101 Gentlemen:

This Information Notice is provided as an early notification of a possibly significant matter. 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 further NRC evaluations so indicate, an IE Circular or Bulletin will be i,ssued *to recommend or request specific licensee actions. If you have questions re*garding this matter, please contact this office.

Sincerely,

~~-

' If. Boyce H. Grier r-Director

Enclosures:

1.

IE Information Notice No. 80-03

2.

List of Recently Issued IE Information Notices CONTACT:

D. L. Caphton (215-337-5339) cc w/encls:

E. N. Schwalje, Manager - Quality Assurance, Engineering and Construction Department 8 0 02 250('fl

ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 SSINS No.:

6870 Accession No.:

7912190666 IE Information Notice No. 80-03 Date:

January 31, 1980 Page 1 of 1

  • . Description of Circumstances:
  • .On September 6, 1.g79, whileperforming.a routinestartup of* the Trojan Nuclear Plant, a speed control problem was encountered during warmup of the General Electric turbine and increase of turbine speed to normal operating speed (1800 RPM).
  • Technicia~s were notified and trouble shooting in accordance with the technical manual was commenced to resolve the apparent oscillation between

. the primary and backup speed control circuits which was hindering normal turbine startup operations. The technical manual indicates that it is permis-sible to remove either the primary or backup low value gate circuits which contain speed and acceleration error amplifiers.

Upon removal of the primary low value* gate circuit card, the backup card amplifiers, coming *from a saturated condition, became the controlling circuit. During the shift in control circuits (primary to backup), the speed/acceleration error signal went to maximum which resulted in a full open signal to the turbine control valves.

Under existing plant conditions this appeared to the safety injection system as a major steam break downstream of.the main steam isolation valves which resulted in a safety injection system actuation and reactor trip.

  • rhe Electrohydraulic Control System (EHC) technical manual indicated that slight load changes are likely when a low value gate card is removed.

The effect on an unloaded turbine appears to be much more significant and tests conducted by Trojan personnel indicate that the transient is initiated whether the turbine is at a set speed or in an acceleration mode to a set speed.

Discussions with General Electric personnel by the licensee have been initiated in an attempt to verify the phenomenon observed and, if applicable, alert other facilities which operate a turbine with a MK 1 EHC System regarding the potential operation of the control valves when trouble ~hooting the speed

.control unit in*accordance with existing instructions.

This information*is provided as an early notification of a possible significant matter. 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 further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.

I.f you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

  • GEK Instruction Book 11381-D, "Speed Control Unit", Maintenance Section, Page
4.

.Information Notice No. 79-28 79-29 79-30 79-31 79-32 79-33 79-34 79-35 79-36 79-37 80-01 80-02 ENCLOSURE 2.

IE Information Notice No. 80-03 Date:

January 31, 1980 Page l of 1

. RECENTLY ISSUED IE INFORMATION NOTICES Subject

. Ovetl oadi ng *of Structural

. Elements Due. to Pipe Support Loads Loss of Nonsafety Related Reactor Coo.lant System In'."'

strumentation During Operation Reporting of Defects and Noncompliances, 10 CFR

. Part 21 Use of Incorrect Amplified Response Spectra (ARS)

Date Issued Issued to 11/16/79 All Power Reactor Faci-lities with an Operating

  • license {OL) or Construction

.* P.ermit (CP).

11/19/79 *All Power Reactor Faci-lities with an OL or CP 12/6/79 All Powe.r Reactor Faci-

.lities with an OL or CP.

12/13/79 All Power Reactor Faci-lities with an OL or CP

. Separatfon of El ectri ca 1 12/21/79. Ali Power Reactor Faei-

. Cables. for HPCI and ADS lities with an OL or CP

  • .Improper Closure of Primary 12/21/79 All Power Reactor Faci-Containment Access Hatches

. 1 ities with an OL or CP Inadequate Design of Safety-12/31/79 A 11 Power Reactor Faci-Related Heat Exchangers lities with an OL or CP Control of Maintenance

. 12/31/79 All Power Reactor Faci-and Essential Equipment lities with an OL or CP Computer Code Defect in 12/31/79 All Power Reactor Faci-

  • Stress Analysis of Piping lities with an OL or CP Elbow Cracking in Low Presssure 12/31/79 All Power Reactor Faci'."'

Turbine Discs liti~s with an OL or CP Fuel Handling Events 1/4/80 All Power Reactor Faci-lities with an OL or CP 8X8R Water Rod Lower 1/25/80 All BWR Facilities with Erid Plug Wear an OL or CP l