ML20150B010

Amend 25 to License NPF-47,increasing Allowable Drywell Temp to 145 F & Area Temp for Main Steam Tunnel to 135 F

ML20150B010
Person / Time
Site:	River Bend
Issue date:	06/29/1988
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20150B014	List: ML20150B010 ML20150B027 ML20150E346
References
NUDOCS 8807110212
Download: ML20150B010 (7)

Text

!

o UNITED STATES

[

[y,h NUCLEAR REGULATORY COMMISSION E

WASHINGTON. D. C. 20555 5

%, e

,o s <*

GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AEh0 MENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. NPF-47

1. The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment filed by Gulf States Utilities Company (the licensee), dated June 5, 1987 as modified May 13, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance:

(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; an(

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the licence is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 25 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8a07110212 880629 PDR ADOCK 05000458 P

PDC

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 8M l

Jose'. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specification t

Date of Issuance:

June 29, 1988 l

l l

l 1

l l

1

ATTACHMENT TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and

-contain vertical lines indicating the areas of change. Overleaf pages are provided to maintain document completeness.

REMOVE INSERT 3/4 6-24 3/4 6-24 3/4 7-33 3/4 7-33 l

[

vit l

l l

l l

3 CONTAIMENT SYSTEMS DRWELL INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.2.5 Drywell-to primary containment differential pressure shall be maintained between - 0.3 and + 1.2 psid.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

t With the drywell-to primary cont'ainment differential pressure outside of the specified limits, restore the differential. pressure to within the limits within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD l

SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l SURVEILLANCE REQUIREMENTS l

4.6.2.5 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the drywell-to-primary containment differential pressure shall be determined to be within the limits.

f a

l RIVER BEND - UNIT 1 3/4 6-23 1

CONTAINHENT SYSTEMS DRWELL AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.2.6 Drywell average air temperature shall not exceed 145'F.

l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the drywell average air temperature greater than 145'F, reduce the l

average air temperature to within.the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.2.6 The drywell average air temperature shall be the arithmetical average of the temperatures at the following locations and shall be determined to be within the limit at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

ELEVATION AZIMUTH a.

• 145' 20' $ A i 60' b.

• 145' 100* $ A $ 150' c.

• 145' 190* $ A 1 265' d.

• 145' 290' 1 A 1 330' l

l RIVER BEM - WIT 1 3/4 6-24 Amendment No. 25

TABLE 3.7.8-1 AREA TDIPERATURE MONITORING AREA TDIPERATURE LIMIT (*F) 1.

Auxiliary Buildina a.

LPCS area 122 b.

RHR A pump roca 122 c.

RCIC pump roca 122 d.

RHR B p g roco 122 e.

RHR C pump roca 122 f.

HPCS pump room 122 g.

MCC area (West) 112 h.

MCC area (East) i 116 1.

Main steam tunnel (north)

I35 l

j.

Staney gas treatment rooms 122 k.

Annulus mixing fan area 122 1.

RHR 16 Area (West) 122 m.

Hoist Area 122 n.

RHR Nx Area (East) 122 c.

HPCS Hatch Area 122 p.

RPCCW Area 122 q.

Elevator Room 122 r.

RPCCW Area 122 s

RHR Equip. Removal Cubicles 122 2.

Diesel Generator Control Rooms a.

Diesel Generator 1A 104 b.

Diesel Generator 18 104 c.

Diesel Generator IC 104 3.

Control Buildino a.

Standby switchgear room 1A 104 b.

Staney switthgear room 18 104 c.

Division I inttery room 90 d.

Division II battery roce 90 e.

Division III battery roos 90 f.

7.nverter 1A room 104 g.

Inverter 18 room 104 h.

Inverter le room 104 i

RIVER SEND - UNIT 1 3/4 7-33 Amendment No. 25 e

l

- - - - - - - - - - - - - - - - - - ~ - - - - - - - - ~ - - ' - -

PLANT SYSTEMS 3/4.7.9 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION i

3.7.9 The main turbine bypass system shall be OPERA 8LE.

APPLICA8ILITY: OPERATIONAL CONDITION 1 (when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER)

ACTION:

With the main turbine bypass system' inoperable, restore the system to OPERABLE 4

status within I hour or be at less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.9 The main turbine bypass system shall be demonstrated OPERA 8LE:

At least once per 7 days by cycling each turbine bypass valve through a.

at least one complete cycle of full travel, and b.

At least once per 18 months hy:

1.

Performing a system functional test which includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.

2.

Demonstrating that TUR8!NE SYPAS$ SYSTEM RESPONSE TIES meet the following requirements when measured from the initial closure movement of the main turbine stop valve or the main turbine cor. trol valve:

a)

Main turbine bypass valve opening shall start within 0.1 seconds, and b) at least 80K of main turbine bypass capacity shall be established within 0.3 seconds.

RIVER 500 - UNIT 1 3/4 7-34

.