ST-HL-AE-2534, Application for Amend to License NPF-71,deleting Surveillance Requirement 4.5.1.1d Requiring Verification That Each Safety Injection Accumulator Isolation Valve Opens Automatically When RCS Pressure Exceeds P-11.Fee Paid

Application for Amend to License NPF-71,deleting Surveillance Requirement 4.5.1.1d Requiring Verification That Each Safety Injection Accumulator Isolation Valve Opens Automatically When RCS Pressure Exceeds P-11.Fee Paid

ML20148C108
Person / Time
Site:	South Texas
Issue date:	03/11/1988
From:	Vaughn G HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20148C112	List: ML20148C117 ST-HL-AE-2534, Application for Amend to License NPF-71,deleting Surveillance Requirement 4.5.1.1d Requiring Verification That Each Safety Injection Accumulator Isolation Valve Opens Automatically When RCS Pressure Exceeds P-11.Fee Paid
References
ST-HL-AE-2534, NUDOCS 8803220278
Download: ML20148C108 (5)

Text

O The Light m m P u y iiees,emi.,x,,es&re<, s r.o.i m iroo iiems,em. 1cxm,21ooi <2isi22s.92ii March 11, 1988 ST-HL-AE-2534 File No.: G20.02.01 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Docurent Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 Proposed Deletien of Technical Soecification 4.5.1.ld.

Pursuant to 10CFR50.90, Houston Lighting & Power (HIAP) hereby proposes to amend its Operating License, NPF-71, by incorporating the attached proposed change to the Technical Specifications, NUREG-1255, for South Texas Unit 1.

We would appreciate your expeditious review of the matter. This charge is not considered an item for the full power Operating License Technial Specifications.

Specifically, H14P is proposing the deletien of Surveillance Requirement 4.5.1.ld. which requires verification that each SI accumulator isolation valve opens automatically when an actual or simulated RCS pressure signal exceeds the P-ll (SI unblock) setpoint, and on an SI signal.

Discussion Since Technical Specification 3.5.1 and 4.5.1.la.2 require that the isolation valves be open with power removed at all times during Modes 1, 2 and 3, with pressurizer pressure above 1000 psig, and that the valves bc verified to be open at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the requirements of 4. 5.1. ld. are unnecessary. When the valves are deenergized, an auto-open signal will be completely ineffective. These valves are interlocked such that:

(1) They open automatically on receipt of an SI signai with the main control board switch in either the "AUT0" or "Close" position, (2) They open automatically whenever the RCS pressure is above the SI unblock pressure (P-ll) and only when the main control board switch is in the "Auto" position, (3) They can not be closed as long as an SI signal is present.

The "maintain closed" position is required to provide an administrative 1y controlled manual block of the automatic opening of the valve at pressure l L2/NRC01/le.

> \

gfCM$ fl50 (

1 l 880322027G 880311 PDH ADOCK 05000498 00\\bY g P DCD

. , ol l ,

ST-HL-AE-2534 File No.: C20.02.01 Page 2 above the' SI unblock pressure (P-ll). The manual block or "maintain closed"

. position is required when performing periodic check valve leakage tests when the reactor is at operating pressure. The valve is closed from the control board by placing it in the "maintain closed" position. Administrative controls are - in place to ensure that any accumulator valves that have been closed at pressures above the SI unblock pressure are returned to the "Auto" position. Additionally, as mentioned previously, Technical Specification 4.5.1.la.2) requires that the isolation valve be verified to be open with power removed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This proposed amendment has already been approved and the surveillance requirement deleted from the Callaway and Vogtle Technical Specifications.

Significant Hazards Considerations The Commission has provided standards in 10CFR50.92(c) for determining -

whether a significant hazards consideration exists. A proposed amendment to an Operating License for a facility involves a no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the 1.robability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) . involve a significant reduction in the margin of safety. HiAP has reviewed the proposed change and determined that:

1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because it does not constitute a change to plant systems which are part of FSAR accident analysis either in failure / accident initiation mode oi accident mitigation mode.

2. The proposed amendment does not create the possibility of a new or  ;

different kind of accident than previously evaluated because it does not constitute a change to plant systems which are part of FSAR accident analysis either in failure / accident initiation mode or accident mitigation mode.

3. The proposed amendment does not involve a significant reduction in the margin of safety for the reasons provided in the discussion above. Additionally, as required by the Limiting condition for Operation, Action b. , if the isolation valve can not be opened after performing check valve leakage tests, the plant must be placed in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Also, inasmuch as the P-ll interlock is tested in accordance with Table 4.3-2, Items 1. and 9a., the testing required by 4.5.1.1d is redundant.

L2/NRC01/le.

l

~ST-HL-AE-2534 File No.: G20.02.01 Page 3-

-Based on-the information contained in this submittal and the NRC Final Environmental Assessment for South Texas Units 1 6 2, H14P has concluded that pursuant to 10CFR51, there are no significant radiological or non-radioloy.ical-

~

impacts ' associated with _ the proposed . action and that the proposed ~1icense amendment will not have ,a significant effect ' on -the quality of the human.

environment.

The South Texas Project Unit 1 Nuclear Safety Review Board has reviewed

~

and approved the attached proposed revision to the Operating License.

In accordance with 10CFR50.91(b), HI4P is providing the State of Texas with a copy of this proposed amendment.

Pursuant to the 1equirements of 10CFR170.12(c), enclosed with .this amendment request is the application fee of $150.00..

If you should have - any questions on this -matter, please contact Ms. F. A.

White at (512) 972-7985.

• (

G. E. Vaughn

-Vice President Nuclear Plant Operations GEV/FAW/yd Attachments: (1) Proposed Deletion of Technical Specification 4.5.1.1d.

(2) FSAR Section 7.6.3 (3) Chack No. 00110371 l

l L2/NRC01/le.

<e.,,

ST-HL-AE-2534 File No.: G20.02.01 Page 4 cc:

Regional' Administrator, Region IV INPO Nuclear Regulatory Commission .

Records Center .

611 Ryan Plaza Drive, Suite 1000 1100 Circle 75 Parkway Arlington, TX 76011 Atlanta, CA 30339-3064 N. Prasad Kadambi, Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Dan'R Carpenter Senior Resident Inspector / Operations c/o U.S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J.R. Newman, Esquire Newman & Holtzinger, P.C.

1615 L Street, N.W.

Washington, DC 20036 R. L. Rangs/R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403' l R. John Miner (2 copies) l Chief Operating Officer

! City of Austin Electric Officer 7221 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt

! City Public Service Board P. O. Box 1771 -

l San Antonio, TX 78296 Rufus S. Scott '

l Associate General Counsel l Houston Lighting & Power Company _

.5 P. O. Box 1700 ..; E 7 Houston, TX 77001 '.,~

l I

l e

l l

l l

g -

UNITED STATES OF AMERICA NUCLEAR REGUIATORY COMMISSION In the Matter ) Operating License NPF-71

) Docket No. 50 493 Houston Lighting & Power )

Company, et al., )

)

South Texas Project )

Unit 1 )

AFFIDAVIT G. E. Vaughn, being duly sworn, hereby deposes and says that he is Vice President, Nuclear Plant Operations, of Houston Lighting & Power Company; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached proposed Technical Specifications amendment regarding the deletion of Surveillance Requirement 4.5.1.ld.; is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge and belief.

WH G. E. Vaughn '

Vice President Nuclear Plant Operations STATE OF TEXAS )

)

)

Subscribed and sworn to before me, a Notary Public in and for the l

State of Texas this //t,f day of h61988.

l Notary Public l /* * *** ANN ALEXANDER

_,_,...s

{ '.g,f Wy Comersson Empres 12.M1 I E . _ __._ s l

l

_ , = .__ -.- . . -.