ML20154N863

Discusses Insp Repts 50-498/88-11 & 50-498/88-24 on 880211- 0331 & 0405-0502 & Forwards Notice of Violation,Per Enforcement Conference on 880526 in Region IV Ofc, Arlington,Tx

ML20154N863
Person / Time
Site:	South Texas
Issue date:	09/21/1988
From:	Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Goldberg J HOUSTON LIGHTING & POWER CO.
Shared Package
ML20154N868	List: ML20154N863 ML20154N885
References
EA-88-112, NUDOCS 8809300025
Download: ML20154N863 (4)

See also: IR 05000498/1988011

Text

- -_

!

l .

c .

.

c W 2l W

l Docket: 50-498

l License No NPF-76

EA No.88-112

Houston Lighting & Power Company

I ATTN: J. H. Goldberg, Group Vice

l President, Nuclear

! P.O. Box 1700

Houston, Texas 77001

Gentlemen:

This refers to the inspections conducted on February 11 through March 31 and

April 5 through May 2, 1968, at the South Texas Project, Unit 1 (STP-1), NRC

Inspection Report Nos. 50-498/88-11 and 50-498/88-24 During these inspections,

NRC personnel reviewed two events that were reported to the NRC and involved

theapparentfailuretosatisfyTechnicalSpecification(TS) requirements.

Following a review of the events, an enforcement conference was held on May 26,

1988, in the Region IV office in Arlington, Texas.

One event involved the operation of STP-1 in Mode 1 in what appeared to be a

condition outside TS Action Statement 3.7.1.6 b which requires that with two

less than the required four steam generator atmospheric steam relief valves

operable, at least three steam generator atmospheric reitef valves should be

restored to uperable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (These valves are norina11y

referred to as steam generator power-operated relief valves (PORVs).) Your

plant staff entered TS 3.0.3 for operational convenience to complete a

self-imposed surveillance requirement to satisfy a safety evaluation for

continued operation which addressed the operability status of the four steam

generator PORVs that had improper BUNA-N seal material installed in the

hydraulic actuators and hydraulic pumps.

Specifically, on April 24, 1988, when steam generator PORVs "A" and "0" were

inoperable, the plant operations staff entered TS 3.0.3, isolated steam

generator PORY "C" for 8 minutes and cycled the valve by remote manual

operation. The plant staff then restored steam generator PORY "C" to automatic

operation status and exited TS 3.0.3. Subsequen*.ly, the plant operations staff ,

again entered TS 3.0.3 isolated steam gen 6rator PORY "B" for 10 minutes and  :

,

cycled the valve by remote manual operation. The plant staff then restored l

!. steam generator PORY "B" to an automatic operation status and exited TS 3.0.3.

The circumstances involved with the testing of the steam generator PORVs did

not make the valves functionally inoperable. In the safety analysis, FSAR

Chapter 15, operation of the steam generator PORVs is assumed in accident I

analysis for mitigation of small break LOCA, feedwater line break, loss of

normal feedwater and loss of offsite power. These events require only manual

operation of the steam generator PORVs to mitigate the conditions in later ,

stages of the events. The TS surveillance requirements for the PORVs requires '

verification that all valves will open and close fully by operation of manual

controls.

l

l

RIV:C:PSD

EJHoller;df

E0

GF

,

rn

D

Lw

Pk

llan

\ l

l 9//f/88 9/l 88 9/g88 '

8309300025 880921 I

l

PDR ADOCK 05000499

( ,

t

Q PDC f

I

.__ . _ __ _ _ . _ .

.

o

.; . .

.

Houston Lighting & Power Company -2-

As a collateral matter, the plant operations staff thought that the testing ,

situation would require the declaration of valve inoperability. This may have  :

been because of the wording of the TS Limiting Condition for Operation ,

associated with the steam generator PORVs. You are encouraged to further

.

investigate this and to initiate a TS change, if appropriate.  :

1

1 Although in this instance there was no immediate concern for the safety of the

1 plant, the NRC considers this event significant,because of the failure of the

plant staff to understand the proper application of TS requirements to the .

operation of STP-1. The plant operations staff made a conscious decision to  !

enter TS 3.0.3 to test the steam generator PORVs. The STP-1 bases explicitly ,

, prohibit the entry into TS 3.0.3 for operational convenience. Although the NRC r

does not believe that it would have been necessary to shut down the operation ,

l of STP-1 in this instance, the NRC does believe that other appropriate I

,

regulatory options, such as enforcement discretion or a temporary waiver of i

~

compliance, were available and should have been pursued. The NRC does not

'

intend to take further action regarding this matter at this time because of

your identification and prompt reporting of this event, your prompt and

i extensive corrective actions ' described during the enforcement conference, and

,

your performance in the area of adherence to TS requirements during the early l

'

phases of plant operation.  !

!

i The violation in the enclosed Notice of Violation addresses the other event

I discussed at the enforcement conference and involves the discovery by Houston  ;

j lighting & Power Company on February 9,1988, that 7 of 12 feedwater flow  :

transmitters were isolated. These feedflow transmitters were part of the '

, Excessive Cooldown Protection System and were required to be in operation by

TS 3.3.2 in Modes 1, 2, and 3. The feedflow transmitters had been isolated

~ '

since April 1987 even though STP-1 had entered Mode 3 on November 22, 1987,

i and January 30 ana February 7,1988, and the facility had operated in that  ;

q mode for several days on each occasion. The NRC considers this event  :

potenthily significant and is concerned that the programatic weakness that i

s

led tc tha feedflow transmitters being isolated could adversely affect other }

l safety-related activities. l

,

1

] The violation described in the enclosed Notice has been classified at a 1

< Severity Level IV. As indicated in Supplement I of the NRC Enforcement

4 policy, significant violations of this type are normally classified at a

j Severity Level III. However, after careful consideration of the fa tors

i involved, this violation has been classified at a Severity Level IV because,

at the time of discovery (before initial criticality - Mode 2), the feedwater

i system had not been operated at a flow rate sufficient for the flow indication ,

to register in the control room; therefore, the licensed operators could not L

have detected that the flow transmitters were isolated by direct observation,

.

i

Further, because the Excessive Cooldown Protection was not required by the ,

1. STP-1 accident analysis, the TS requirement was deleted on May 24, 1988.  !

i  !

i

i

J

l

i

,

. . .

.

Houston Lighting & Power Company -3-

i

You are required to respond to this letter and should follow the instructions  !

specified in the enclosed Notice when preparing your response. In responding,

'

you may refer to previous correspondence to the NRC where you have documented .

,

all or part of your required response to this violation. In your response, ,

you should document the specific actions taken and any additiont.1 actions you l

plan to prevent recurrence. After reviewing your response to this Notice, i

including your proposed corrective actions and the results of future  ;

'

inspections, the NRC will determine whether further NRC enforcement action is

necessary to ensure compliance with NRC regulatory requirements.

i

In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, ,

Title 10, Code of Federal Regulations, a copy of this letter and the enclosures l

will be placed in the NRC's Public Document Room.  !

The responses directed by this letter and the enclosed Notice are not subject i

to the clearance procedures of the Office of Management and Budget as required '

by the Paperwork Reduction Act of 1980, Pub. L. No.96-511.

,

Sincerely, j

!

l

!

L. J. Callan, Director

Division of Reactor Projects l

Enclosure:  !

Appendix - Notice of Violation j

cc w/ enclosure:

Houston Lighting & Power Company Newman & Holtzinger, P.C. l

ATTN: M. A. McBurnett, Manager ATTN: J. R. Newman, Esquire f

Operations Support Licensing 1615 L Street, N.W.  !

P.O. Box 289 Washington, D.C. 20036 l

Wadsw,eth, Texas 77483 ,

Houston Lighting & Power Company Houston Lighting & Power Company

ATTN: Gerald E. Vaughn, Vice President ATTN: S. L. Rosen

Nuclear Operations P.O. Box 289

P.O. Box 289 Wadsworth, Texas 77483

Wadsworth, Texas 77483

Houston Lighting & Power Company Houston Lighting & Power Company

ATTN: J. T. Westermeier, General Manager ATTN: R. W. Chewning, Chairman

South Texas Project Nuclear Safety Review Board

P.O. Box 289 P.O. box 289

Wadsworth, Texas 77483 Wadsworth, Texas 77483

.

. . - . _ , . -

_

-

-

.

<

. .. ,

0

.

Houston Lighting & Power Company -4- '

Central Power & Light Company City Public Service Board

ATTN:. R. L. Range /R P. Verret ATTN: R. J. Costello/M. T. Hardt

P.O. Box 2121 P.O. Box 1771

Corpus Christi, Texas 78403 San Antonio, Texas 78296

City of Austin Electric Utility Houston Lighting & Power Company

ATTN: R. J. Miner, Chief Operating ATTN: Licensing Representative

i Officer Suite 610

!

721 Barton Springs Road Three Metro Center '

Austin, Texas 78704 Bethesda, Maryland 20814

Texas Radiation Control Program Director

bectoDMB(IE01)

bec distrib. by RIV:

i

'

DRP RRI-OPS

R. D. Martin, RA DRS '

i

SectionChief(DRP/D) RPB-DRSS-  ;

1 MIS System RIV File r

Lisa Shea, RM/ALF RSTS Operator

R. Bachmann, OGC D. Hunnicutt i

G. Dick, NRR Project Manager Project Engineer, ;RP/D '

'1

RRI-CONST G. Sanborn

J. Lieberman, OE J. Luehman, OE  ;

'

1

f

i

i

d

i

4

4

I

- _ . . _. . . - _ _ _ , , - _ . _ . , - _ _ _ - _ - . _ . _ . . - - . _ . - . _ . _