ML20032B045

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IE Insp Repts 50-295/81-22 & 50-304/81-18 on 810915 & 21-24. Noncompliance Noted:Failure to Develop Test Criteria Necessary to Ensure That Same Stds Apply to Modified as to Original Design Circuits.Mods Relate to 810914 Event
ML20032B045
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 10/15/1981
From: Baker K, Connaughton K, Gildner M, Peschel J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20032B038 List:
References
50-295-81-22, 50-304-81-18, NUDOCS 8111040324
Download: ML20032B045 (10)


See also: IR 05000295/1981022

Text

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U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Reports No. 50-295/81-22; 50-304/81-18

D<,cket Nos. 50-295; 50-304

Licenses No. DPR-39; DPR-48

Licensee:

Commonwealth Edison Company

Post Office Box 767

Chicago, IL 60690

Facility Name: Zion Nuclear Power Station, Units I and 2

Inspection At: Zion, IL

Inspection Conducted: September 15 and 21-24, 1981

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Inspectors:

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gR. Baker, Chief

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Approved By:

Management Programs Section

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Inspection Summary

Inspection on September 15 and 21-24, 1981 (Reports No. 50-295/81-22;

50-304/81-18)

Areas Inspected: The inspection at Zion was a special inspection conducted

to followup on the Preliminary Notification - PNO-III-81-79 of September 15,

1981, (LER 50-304/81-20) and to review modifications M22-1-80-24 and M22-2-80-24.

The inspection involved 56 inspector-hours onsite and 22 inspector-hours in

office by three NRC inspectors.

Results: One item of noncompliance was identifed by the inspectors'; failure

to develop test criteria in accordance with Quality Procedure 3-51 of the

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Commonwealth Edison Quality Assurance Program.

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DETAILS

1.

Persons Contacted

  • K. Graesser, Plant Superintendant
  • E. Fuerst, Operating Assistant Superintendant

R. Budowle, Operating Engineer

  • E. Campbell, Technical Staff

S. llazelrigg, Technical Staff

P. LeBlond, Assistant Technical Staff Supervisor

A. Miosi, Technical Staff Supervisor

T. Lukens, Quality Control Supervisor

  • J. Murphy, Quality Control
  • B. Harl, Quality Assurance

J. Deress, Station Nuclear Engineering Department

  • Denotes those attending the exit interview of September 23, 1981.

The inspectors also interviewed other licensee employees including

members of the Technical, Operations, and SNED staffs.

2.

Review of Modifications M22-1-80-24 and M22-2-80-24

The inspectors reviewed the modification packages to determine whether

or not the proposed modification had received proper review in accord-

ance with 10 CFR 50.59; 10 CFR 50, Appendix B, Criterion III, " Design

Control;" the licensee's approved Quality Assurance Program and other

licensee commitments. The inspectors also reviewed design drawings

and specifications to assess what additional impact, if any, the mod-

ification may have had on the operability of affected components from

the time of installation until corrective action was taken following

the September 14, 1981 event (PNO-III-81-79) later reported as

LER 50-304/81-20.

a.

Background

on May 15, 1980, during performance of safeguards testing at

Zion 1; the 1A Service Water pump failed to automatically start

on command. The cause was determined to be a faulty Westinghouse

Type W-2 control switch. The switch's contacts, in the neutral

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(automatic) position did not provide electrical continuity for

the automatic start signal path. Subsequent tests revealed that

contact closure was intermittent. Westinghouse, manufacturer of

the switch, was notified of the problem and they performed a

review. The results of the review were transmitted in NSD

Technical Bulletin No. 80-9 to all utility owners of Westinghouse

operating plants. The technical bulletin recommended that all

switches be tested for continuity in the neutral position initially

and subsequently after each manipulation (removal from the neutral

position). As an alternative Westinghouse also proposed that the

green breaker position indicator light be rewired to monitor contact

status in the neutral position. Subsequently the NRC Office of

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Inspection and Enforcement issued IE' Bulletin No. 80-20 which

directed licensees of operating plants using Type W-2 switches in

safety-related systems to test the switches fo+ continuity in the

neutral position within ten days of the date c. wae bulletin

(July 31, 1980), at least once every 31 days after the initial

test and after each manipulation of the switch. Furthermore, the

bulletin required long term corrective action consisting of as a-

minimum, the design change described in Westinghouse Techncial

Bulletin No. 80-9.

Licensees were required to submit a description

of plans for longer term corrective measures within forty-five days

of the date of receipt of the IE Bulletin.

Commonwealth Edison, in a response letter dated September 15,

1980, stated that a modification had been initiated to rewire the

indicator lights so both the red and green lights would be used

for checking continuity of the neutral contacts. At that time,

no further oetail concerning the modification was provided.

Commonwealth Edison performed the modification on approximately

fourty-six switches between October 2 and October 16, 1980.

Figure 1 shows a simplified, typical control circuit before and

after modification.

(NOTE: Refer to Table 1 for an explanation

of schematic symbols and nomenclature). After the modification

it was observed that in the trip and' pull-to-lock switch positions

both the red and green breaker position indicating lights were

dimly lit. A sneak power path was discovered at that time which

is shown in Figure 2.

The sneak path was confirmed and was con-

sidered merely a nuisance. A Modification Training Summery was

written that described the new manner of indicator light operation,

including the dimly lit re6 and green lights in the trip and

pull-to-lock positions.

On September 14, 1981 during normal cooldown on Unit 2, with RHR

in' service to control temperature, Steam generator level was

allowed to fall below the 10% low low level resulting in an auto

start signal to the Auxiliary Feedwater Pumps (AFP). The opera-

tors placed the AFP Control Switches in the pull-to-lock position

as allowed by procedure, to avoid excessive cooldown. The pumps

tripped as restired. Subsequently, the operators attempted to

restart one of the motor-driven auxiliary feedwater pumps. The

pump motor could not be started. Attempts to start the other

motor driven auxiliary feedwater pump also failed. An unrelated

problem prevented the steam supply valve to the turbine driven

auxiliary feedwater pump from opening upon demand rendering the

turbine driven pump inoperable. One motor driven auxiliary

feedwater pump was successfuly started after the four KV supply

breaker had been racked out and then returned to service. The

motor drivea auxiliary feedwater pumps' failure to start was

determined to be a result of the modification to the W-2 type

control switch +s.

Figmre 3 for the following discussion)

(NOTE:

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The modification resulted in the preseace of an additional sneak

circuit, when an automatic start signal was present, that carried

sufficient current to the lockout relay (Y) coil of the breaker

to prevent lockout relay contacts from changing status if the

breaker was tripped.

The lockout relay contacts must change status when the breaker

is tripped to allow the iatch release (X) coil to be energized

and reclose the breaker on demand. With the breaker tripped in

the presence of an auto start signal, reclosure can be achieved

if the sneak circuit is temporarily interrupted, allowing the

lockout relay contacts to change status. Racking out and return-

ing to service the auxiliary feedwater pump breaker accomplished

this and restored the pump-to operable status.

Upon determination of the sneak path which affected the motor

driven auxiliary feedwater pumps, the licensee removed local

breaker position indicator light bulbs which were part of the

sneak path. Local breaker position indicator light bulbs were

removed from all control circuits affected by the modification,

thereby eliminating the possibility of any similar occurence

until a new modification to permanently resolve the problem is

accomplished. Caution tags were hung to prevent inadvertant

installation of local breaker position indicator light bulbs in

the interim.

b.

Findings

Noncompliance (50-295/81-22-01) (50-304/81-18-01)

The modification received re sw by the required station

personnel and was sent to the Station Nuclear Engineering

Department, (SNED), with a transmittal letter, dated July 30,

1980, requesting modification review per Quality Procedure 3-51

(QP 3-51).

According to QP 3-51 SNED has the responsibility for preparing

required detailed engineering design documents including the

safety analysis required by 10 CFR 50.59, necessary drawings,

quality requirements and other supporting documentation require-

ments. Also SNED is required to provide all test criteria,

functional descriptions and engineering information necessary te

prepare the required test procedures.

SNED was provided with functional descriptions by Sargent and Lundy,

by a letter 4:ted August 18, 1980, documenting Sargent and Lundy's

review of the ptcpose modification.

SNED documented it's modification review as having been performed

in accordance with QP 3-1 in a letter dated August 19, 1980. The

letter also made a recommendation that every affected circuit be

functionally tested before it is placed in service. However no

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test criteria was provided. The failure of SNED to provide

specific test criteria in accordance with Quality Procedure 3-51

is an item of noncompliance identified in Appendix A.

c.

Discussion

(1) The Zion Technical Staff chose not to follow the SNED re-

commendation and performed the modification with a step by

step wiring procedure followed by a continuity check which

constituted the test. The licensee stated that a recom-

mendation from SNED does not have to be followed and sound

engineering judgement and experience was used in the pre-

paration of the modification. The licensee also maintained

that Performance Tests were probably run on each item of

equipment af ter the modification, but could not produce any

documentation to substantiate the belief.

The inspectors prescated their position that SNED should not

be making recommendations, but should be following QP 3-51

and supplying criteria for testing. They stated that had a

functional test been performed to demonstrate as a minimum,

conformance with the functional descriptions, the glowing

red and green indicator lights in the trip and pull-to-lock

position would have met the definition of a Discrepant Item,

defined in Quality Procedure 15-53.

" Nonconforming Materials,

Parts and Components for Operation - Inspection and Test."

A Discrepat:. Item is defined as an item that does not

conform to its inspection'and testing requirements defined

in the engineering and design specifications. Corrective

action for a Discrepant Item is initiated by the issuance

of a Discrepancy Record.

Since there was no test failure, a Discrepancy Record was not

required to be written in this case. The Licensee closed the

Action Item Record on the modification on October 16, 1980 and

did not show docmentation of act on on the dim lights until

January 7, 1981, when a new modriication designated ' low

priority' was initiated. The new modification was not con-

sidered vital for the Operation of the plant so an Action Item

Record (AIR) was not initiated for the new modification and

consequently the corrective action was not accomplished in a

timely manner.

The inspectors stated that had a Discrepancy Record been

initiated upon the discovery of the nonconforming condition

the event of September 14, 1981, could possibly have been

prevented since the stated purpose of the Corrective Action

System is to accomplish corrective action in a timely manner

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and the operationa? implications of the sneak circuit may

have been identified and corrected prior to causing an

operational event such as reported in the LER.

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'(2) SNED personnel stated that the modification had been

reviewed by both QP 3-1 and QP 3-51 as is their normal

procedure and the ommission of QP 3-51 in their letter

was a typographical error which would be corrected.

The inspectors had no further questions at this time.

3.

Exit Interview

The inspectors met with licensee representatives denoted in Paragraph 2

at the conclusion of the inspection on September 24, 1981. The inspec-

tors summarized the purpose, scope and findings of the inspection.

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TABLE 1

' Legend for" Figures 1-3

CS-

-Control Switch

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Lockout Relay Contacts

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Iuxilliary contacts:

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Safeguards Contacts -(Closed for Auto-Start)

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Contacts

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Latch Reicase Coil

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Lockout Relay Coil

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