ML19260C606

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Forwards IE Info Notice 79-32, Separation of Electrical Cables for HPCI & Automatic Depressurization Sys. No Specific Action or Response Requested
ML19260C606
Person / Time
Site: Humboldt Bay, Diablo Canyon
Issue date: 12/21/1979
From: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Crane P
PACIFIC GAS & ELECTRIC CO.
References
NUDOCS 8001080090
Download: ML19260C606 (1)


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UNITED STATES

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,,e WALNUT CREEK, CALIFORNI A 94596 December 21, 1979 Docket Nos. 50-133, 50-275, 50-323 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention: Mr. Philip A. Crane, Jr.

Assistant General Counsel Gentlemen:

This Information Notice is provided as an early notification of a possibly significant matter. No specific action or response is requested at this time. However, we anticipate that further NRC evaluations will result in issuance of an IE Circular, Bulletin, or NRR Generic Letter in the near future which will recommend or request specific applicant or licensee actions.

If you have any questions regarding the matter, please contact the Director of the appropriate NRC Regional Office.

Sincerely, o%e d'-R.H.

gelken Director

Enclosures:

1.

IE Information Notice No. 79-32 2.

List of Recently Issued Information Notices cc w/ enclosures:

W. Barr, PG&E W. Raymond, PG&E R. Ramsay, PG&E, Diablo Canyon E. Weeks, PG&E, Hurr.boldt Bay J. Worthington, PG&E 1702 016 800108o O%

UNITED STATES SSINS No.: 6870 NUCLEAR REGULATORY COMMISSION Accession No:

0FFICE OF INSPECTION AND ENFORCEMENT 7910250511 WASHINGTON, D.C.

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c, December 21, 1979 uoJ 2

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IE Information Notice No. 79-32 SEPARATION OF ELECTRICAL CABLES FOR HPCI AND ADS This notic) contains information on boiling water reactors (BWR's) regarding the routing of high pressure coolant injection (HPCI) system and automatic depres-surization system (ADS) cables in the same cable tray.

Such routing violates design criteria for separation of these safety systems. This potential cable separation problem for BWR's is highlighted as a result of our review of recent Licensee Event Reports (LER's):

Hatch Units 1 & 2, Brunswick Unit 1, and James A. FitzPatrick (See references for LER identification).

Description of Circumstances:

The Hatch LER's state that the NSSS supplier (General Electric) contacted plant management about possible irregularities in cable separation between HPCI and ADS.

Plant engineering personnel subsequently confirmed that separation criteria per design notes' were not met because HPCI system inboard steam supply isolation valve cables were routed with ADS control cables.

The architect-engineer (AE) was notified of the HPIC/ ADS cable separation problem and they are formulating a design change to provide for proper cable separc tion.

Other, immediate corrective action was not provided in the LER.

The Brunswick LER states that cables for the HPCI system steam supply inboard isolation valve are located in sections of cable trays containing ADS cables.

Also, their analysis of those cables revealed that if the isolation valve were in the wrong position, then a failure at a tray section containing these cables might result in a combination of cable failures which could impair the operability of both the HPCI and ADS systems. The problem is common to both units at Brunswick.

The AE, United Engineers and Constructors, is said to be preparing plant modifi-cations to provide sufficient isolation of HPCI and ADS cables.

The licensee stated that a review of emergency core cooling systems (ECCS) and their primary containment isolation valves is being performed to verify that o other cable separation problems exist. Also, the cable separation criterion for HPCI and ADS systems is to be redefined in the cable separation specifications to prevent future recurrences of this event.

The FitzPatrick plant staff was informed of the HPCI/ ADS cable routing problem by the AE, Stone and Webster, following a fire hazard analysis conducted by the AE.

Six cables which could affect the control of the steam supply inboard isolation valve for the HPCI system are located in the same cable trays as some ADS cables.

Initial corrective action by the licensee to preclude spurious closure of the HPCI system inboard steam supply isolation valve was to de-energize the valve by racking out the breaker.

In addition, for purposes of primary containment isolation, the outboard valve was maintained in its normal, closed position 1702 017

IE.Information Motice No. 79-32 December 21, 1979 Page 2 of 2

  • and checked daily. However, re-evaluation of the initial corrective action indicated the preferred method of assuring operability of both the ECCS and primary containment isolation functions would be to provide additional orotection against a fire which might involve cables of both the HPCI and ADS, and to restore the inboard isolation valve to a fully operable condition. Accordingly, FitzPatrick initiated an hourly patrolling fire watch and restored the inboard isolation valve to a fully operable condition. The hourly patrolling fire watch parallels that required by Technical Specifications when early warning protection against a potential fire must be taken due to inadequate or inoperable fixed detection systems.

The FitzPatrick plant staff was also informed by Stone and Webster that other (third party) cables (not identified in the LER) could affect the operation of the inboard isolation valve for the HPCI steam supply due to their proximity to both HPCI and ADS cables. The licensee has decided to re-route the cables of concern to correct-both problems, and states that a preliminary design modification has been completed.

Conclusions Our review indicates that lack of separation of HPCI and ADS cables is a possible generic problem for al' BWR4's and that earlier designs may also be affected.

Permanent resolution of chis problem, corrective action in the meanwhile, and separation from other systems such as RCIC or isolation condenser are under consideration by the NRC.

It is anticipated that further NRC evaluations will result in issuance of an IE Circular, Bulletin, or NRR generic letter in the near future which will recommend or request specific applicant or licensee actions.

This Information Notice is provided to inform licensees of a possible significant matter.

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

No written response to this Information Notice is required.

References:

1.

Hatch 1, LER #79-056/0IT-0, dated September 11, 1979 2.

Hatch 2, LER #79-098/0IT-0, dated September 11, 1979 3.

Brunswick 1, LEP,#79-068/0IT-0, dated October 9, 1979 4.

FitzPatrick, LER #79-056/0IT-0, dated October 9,1979 5.

FitzPatrick, LER #79-056/0IT-1, dated November 19, 1979 1702 018

IE Information NoticezNo. 79-32 Er, closure December 21, 1979 RECENTLY ISSUED IE INF0PJ4ATION NOTICES Information Subject Date Issued To Notice No.

Issued 79-31 Use of Incorrect Amplified 12/13/79 All holders of power reactor Response Spectra (ARS)

OLs and cps 79-30 Reporting of Defects and 12/6/79 All power reactor facilities Noncompliance,10 CFR Part 21.

holding OLs and cps and vendors inspected by LCVIP 79 9 Loss of NonSafety-Related 11/16/79 All power reactor facilities Reactor Coolant System holding OLs or cps Instrunentation During Operation 79-28 Overloading of Structural 11/16/79 All power reactor facilities Elements Due to Pipe Support with an OL or CP Loads 79-27 Stean Generator Tube 11/16/79 All power reactor facilities Ruptures At Two PWR holding OLs and cps Facilities79-12A Attenpted Damage To New 11/9/79 All Fuel Facilities, Fuel Assenblies research reactors, and power reactors with an OL or CP 79-26 Breach of Containment 11/5/79 All power reactor facilities Integrity holding OLs and cps 79-25 Reactor Trips At Turkey 10/1/79 All power facilities with Point Units 3 And 4 an OL or a CP 79-24 Overpressurization Of 10/1/79 All power reactor facilities Containmentz0f A PWR Plant with a CP After A liain Steam Line Break 79-23 Emergency Diesel Generator 9/26/79 All power reactor Lube Oil Coolers facilities holding OLs and cps 79-22 Qualification of Control 9/14/79 All power reactor Systems facilities with operating licenses and construction permits.

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