ML20147E350

Application for Amend to License NPF-47,revising Main Steam Safety/Relief Valve Safety (Spring) Set Pressure Tolerance

ML20147E350
Person / Time
Site:	River Bend
Issue date:	02/18/1988
From:	Deddens J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20147E354	List: ML20147E350 ML20147E369
References
RGB-27461, NUDOCS 8803070041
Download: ML20147E350 (7)

Text

, ,

)

.~

GULF STATES UTfLITIES C'O NfPANY RfvlR SCND STATION POST C4FICE BOX 220 . ST. FRANCISvlLLE LOUIS!ANA 70775 AREA CODE 504 635 6094 34 4 6651 February 18, 1988 RBG-27461 File Nos. G9.5, C9.8.9.6 U.-S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

River Bend Station - Unit 1

-Docket No. 50-458 Gulf States Utilities. (GSU) Company hereby files' an amendment to the River Bend Station Unit 1 Facility Operating License NPF-47, pursuant to 10CFR50.90. ~This- application is filed to revise the Main Steam Safety / Relief Valve safety (spring) set pressure tolerance. The attached information includen proposed revisions to the River Bend Station technical specification and justifiestions for this change.

Pursuant to 10CFR170.12, GSU has enclosed a check ir the amount of one hundred fif ty dallars ($150.00) for the license omendr.ent applicatica fee. .Your prompt attention to this spplication is appreristed.

Sincerely, l ** V J. C. Daddens Senior Vice President s River Bend Nuclear Group JCD[ B ch Attachment ec: U.S. Nuclear Regulatory Commission 611-Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Senior Resident Inspector Post Office Box 1051 St. Francisville. LA 70775 P 0!

8803070041 880218 PDR ADOCK 05000458 f0 /

DCD P tb Qlc/ftC[ L{ l L f 0//Yl0$b

Ae- <

.q,'. ; : ,, '

_1 s ce Ab  ;

v, . . -

+

< ~y;,. K:n.. .

u in .1 j.

.. , s

~

. -Mr. William H. Spell Administrator-

. . Nuclear: Energy;. Division

~

, , (.: .

~ Louisiana Department of

, Environmental Quality. ,

,G., -

=c

, P.O. Box 146903

Baton Rouge,.LA:70898. <

L &

7 Y p

I h

L v

\

7 f 4 f) T :., l

,P F

1

^

3

.I i 1  ?

g,.

i a

< .g l

F i

d l

l l

i t' e

5 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA )

PARISH OF WEST'FELICIANA )

In the Matter of ) Docket No. 50-458 50-459 GULF STATES UTILITIES COMPANY )

(River Bend Station, Unit 1)

AFFIDAVIT J. C. Deddens, being duly sworn, states that he is a Senior Vice President of Gulf States Utilities Company; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents axe true and correct to the best of his knowledge, informat:on and belief.

/ W' J, b. Deddens Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this / h M day of 6brd CLf7' / , 19 .

~

) .

./1L  : ju M-d" W

[,Joan W. Middlebrooks Notary Public in and for West Feliciana Parish, Louisiana My Commission is for Life.

. j(

ATTACHMENT 1

' GULF STATES.-UTILITIES COMPANY

. RIVER BEND STATION.

DOCKET 50-458/ LICENSE NO. NPF-47 MAINSTEAM SATITY RELIEF VALVES LICENSING DOCUMENT INVOLVED: Technical Specification ITEM: 3.4.2.1 PAGE 3/4 4-7 REASON FOR REQUEST:

-This request to amend.the River Bend Station (RBS)' Safety / Relief _ Valve Technical Specification is submitted pursuant to 10CFR50.90. A quantity of 16 Safety / Relief Valves (S/RV's) of the Crosby type are mounted on the 4 main steam lines and provide overpressure protection for the Reactor Coolant Pressure Boundary (RCPB). The current Technical ' Specification 3.4.2.1 requires that the~ safety valve function of the S/RV's operate within a tolerance of i 1% of the set pressure. The current Safety Analysis Report (SAR) 5.2.2.10 and General Electric Design Specification requires that the safety valve function ~of the S/RV's operate within a tolerance of (+)0 to (-)2% of the set pressure.

~

It is requested that the commission grant amendment to the Technical Specification to agree with the NRC accepted SAR.

-DESCRIPTION OF REQUEST:

Tne 16 S/RV's installed during refueling outage 1 were transported to the manufacturer for inspection and testing. The manufacturer tested and inspected the S/RV's in accordance with their modification and~ testing procedure. The S/RV's were then returned for_ installation in refueling outage 1. Upon review of the test data, it was discovered that 2 of the 16 S/RV's did rot meet the i 1% set pressure tolerance required by

-Technical Specification 3.2.2.1 however, they did meet the (+)0 to (-)2%

set pressure tolerance as estnblished in the SAR and the reactor vendor, General Electric, design specification. Upon review of the manufacturer's modification and testing procedure, it was discovered that it required a set pressure tolerance of (+)0 to (-)2% which conflicts with the Technical Specification Requirements.

It was determined that the 2 S/RV's would perform their safety function properly. They were installed and connected, but they have been declared administratively inoperable due to not meeting Technical Specification requirements. The current Technical Specification 3.4.2.1 requires that the safety valve function of the S/RV's operate within a tolerance of +

1% of the set pressure. The current Safety Analysis Report (SART 5.2.2.10 and General Electric Design Specification requires that the safety valve function of the S/RV's operate within a tolerance of (+)0 to

(-)2% of the set pressure. It is requested that Technical Specification Section 3.4.2.1 be changed to require a (+)0 to (-)2% set pressure tolerance instead of + 1% as currently shown.

1

NO. SIGNIFICANT HAZARDS CONSIDERATION:

It has been determined that adopting the SAR requirements will not-impact system . operability because the change effects the spring (s,1f e t y function) set pressure. The S/RV's. also have a relief function set pressure which activates the.S/RV's via pneumatic actuators at least 42 PSIG lower than the lowest spring set pressure-(see Table 5.2-2 from the SAR). In fact,- this program change will establish a more conservative approach to system operability by changing the set pressure tolerance from + 1% to (+)0 to (-)2%. ,

Specific set pressure tolerances for S/RV's do not exist in the regulatory basis. However, investigation into RBS site specific analysis

. reveals that the S/RV safety function set pressure tolerance (+)0 to

(-)2% is required.

~

In accordance with the requirements of 10CFR50.92, .the following discussions are provided in support of the determination that no significant hazards are created or increased by the changes proposed in this submittal.

- The change proposed by this submittal would not increase the probability or the consequences of a previously evaluated accident because:

This chanFe has been determined to be more conservative by lowering

{ the allowable S/RV setpoint tolerance by 1 percent, and agrees with the originally analyzed conditions presented in SAR 5.2.2.10 and reviewed by the staff in the Safety Evaluation Report (NUREG-0989) and therefore will not affect the response of the plant or equipment required for safety.

- The change proposed by this submittal would not create the possibility of a new or different kind of accident from any previously evaluated because:

The propose! change has been previously evaluated in the SAR 5.2.2.10 and will maintain the plant response within all previous analysis.

This proposal as submitted would not involve a significant reduction in the margin of safety because:

The reduction in the allowable S/RV setpoint tolerance will act to increase, not decrease, any existing margin of safety. This proposed change does not reduce the margin of safety as defined in the basis of the Technical Specification.

r

~The. proposed amendment, as' discussed above, has not changed ~the system de, sign,.' function and operation contained in the SAR and therefore, will

, not increase the probability or the . consequences of. a previously

' evaluated event or will not create a new or different event. Since the ability to perform, as described in the SAR, is maintained by this change, the proposed changes do not result in a significant reduction' in the margin of safety. GSU proposes that_'no significant hazards are involved.

REVISED' TECHNICAL SPECIFICATION' As . indicated above, ' River Bend Station is currently in compliance with the applicable Technical Specification. The proposed changes are provided in the Enclosure.-

SCHEDULE TO ATTAIN COMPLIANCE Two of the 16 S/RV's have been declared INOPERABLE with the remaining'14 valves OPERABLE. Specification 3.4.2.1 allows continued operation in this configuration but GSU requests prompt attention'to this amendment to allow the valves in question to be returned to service.

NOTIFICATION OF STATE PERSONNEL A copy of the: amendment application and this submittal has been provided to the State- of Louisiana, Department of Environmental Quality-Nuclear Energy Division.

. ENVIRONMENTAL IMPACT APPRAISAL Revision of the Technical . Specification does not result in- e.n environmental impact beyond that previously analyzed. Therefore, an approval of this amendment does not resu1*: in a significant environment impact- nor does it change any previoun environmental impact statements for Rivor Bend Station.

pp. - n - . .. .

I V

e .,

ENCLOSURE a

w 5

5 l

i

._ ~- .}