Text

Amend 33 to License NPF-38,changing Tech Specs by Revising Limiting Conditions for Operation on Shutdown Margin W/Ceas Withdrawn & W/Ceas Inserted
	ML20148G179
Person / Time
Site:	Waterford
Issue date:	03/21/1988
From:	Calvo J; Office of Nuclear Reactor Regulation
To:	;
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ML20148G183	List: ML20148G179;
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	NUDOCS 8803290058
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UNITED tiTATE 9 i'

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NUCLEAR REGULATORY COMMISSION C

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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382

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WATERFORDSTEAMELEQTRiCSTATION, UNIT,3 AMEN 0 MENT TO FACILITY CPERATING' LICENSE

.Ar.ende nt No. 33 4

License No. NPF-38 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

he appl 4ation for amendment by Louisiana Pover e, d Light l

Conipany (the licensee) dated August 28, 1987, complies with the standards cad requirements of the Atomic Energy Act of 1954, 1

as amended (the Act), and the Commission's rules and regulations set forth in 10 LFR Chapter I; B.

The facility will operate in conformity with the application, the provisiun<; of the Act, and the rules and regulations of the Cor;cission; C.

There i', reasonable assurance (i) that the activities authorized by thh dmondrent can be conducted without endangering the health and n fety of the public, and (ii) that such activitier will be conducted in compliance with the Comaission's.regulaticas; D.

The issuance of this amendment will not be ininical to the common defense and security or to the health and safety of the public; and E.

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

8803290058 880321 PDR ADOCK 05000382 P

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Accordingly, the license 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-38 is hereby amended to read as fol*,0ws:

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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Drotection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION d. $cvNm>

Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 21,1988 i

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ATTACHVENT TO LICENSE AMEt!DMENT N0. 33 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain decurent completeness.

Remove Insert IV IV 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-3a 3/4 1-3a i

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r INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAff 2.1 SAFETY LIMITS 2.1.1

. REACTOR C0RE.............................................

2-1 2.1.1.1 0NBR....................................................

2-1 2.1.1.2 PEAK LINEAR HEAT RATE....................................

2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE..........................

2-1 4

2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 R E ACTO R T RI P S ETP0lNTS.....................................

2-2 BASES PAGE

_S_E CT ION 2.1 SAFETY LIMITS l

2.1.1 REACTOR C0RE...............................................

B 2-1 2.1.2 RE ACTOR COOLANT SYSTEM PRESSURE............................

B 2-2 i

2.2 LIMITING ;;.

i SYSTEM SETTINGS 2.2.1 REACT 0" '"IP SETP0lNTS.....................................

B 2-2 i

4 WATERf0R0 - UNIT 3 III AMEN 0 MENT NO. 5

N-t INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4 0-1 3/4.0 APPLICABILITY..............................................

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL 3/4 1-1 SHUT 00WN MARGIN - ANY FULL LENGTH CEA WITHORAWN......

SHUTOOWN MARGIN - ALL' FULL LENGTH CEAS FULLY INSERTED 3/4 3/4 1-4 MODERATOR TEMPERATURE COEFFICIENT....................

3/4 1-5 MINIMUM TEMPERATURE FOR CRITICALITY..................

3/4.1.2 B0 RATION SYSTEMS 3/4 1-6 FLOW PATHS - SHUT 00WN................................

3/4 1-7 FLOW PATHS - 0PERATING...............................

3/4 1-8 CHARGING PUMPS - SHUT 00WN............................

3/4 1-9 CHARGING PUMPS - 0PERATING...........................

3/4 1-10 BORIC ACIO MAKEUP PUMPS - SHUT 00WN...................

3/4 1-11 BORIC ACID MAKEUP PUMPS - OPERATING.................

3/4 1-12 BORATED WATER SOURCES - SHUT 00WN.....................

3/4 1-14 BORATED WATER SOURCES - 0PERATING....................

3/4 1-15 BORON 0!LUTION.......................................

3/4.1.3 MOVABLE CONTROL ASSEMBLIES 1

3/4 1-18 CEA P0SITION.........................................

3/4 1-21 POSITION INDICATOR CHANNELS - OPERATING..............

3/4 1-22 POSITION INDICATOR CHANNELS - SHUT 00WN...............

3/4 1-23 CEA DROP TIME........................................

3/4 1-24' SHUTOOWN CEA INSERTION LIMIT.........................

3/4 1-25 REGULATING CEA INSERTION LIMITS......................

3/4 1-28 PART-LENGTH CEA INSERTION LIMITS.....................

AMENDMENT NO.ZI,33; IV WATERFORD - UNIT 3

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3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL SHUT 00WN MARGIN - ANY FULL LENGTH CEA WITHDRAWN LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTOOWN MARGIN shall be greater than or equal to 5.15%

delta k/k when T,yg is greater than 200 F or 2.0% delta k/k when T is less avg than or equal to 200 F.

APPLICABILITY:

MODES 1, 2*,

3, 4, and 5 with any full length CEA fully or partially withdrawn.

ACTION:

With the SHUTDOWN MARGIN less than that required above, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution con-taining greater than or equal to 1720 ppm boron or equivalent until the required SHUiDOWN MARGIN is restored.

l SURVEILLANCE REQUIREMENTS 4.1.1.1.1 With any full length CEA fully or partially withdrawn, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that required above:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the.CEA(s) is inoperable.

If the inoperable CEA is immovable or untrippable, the above required i

SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable CEA(s).

b.

When in MODE 1 or MODE 2 with Keff greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that CEA group withdrawal is within the Transient Insertion Limits of Specification 3.1.3.6.

c.

When in MODE 2 with K less than 1.0, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to gff achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.

s See Special Test Exception 3.10.1.

WATERFORD - UNIT 3 3/4 1-1 AMENDMENT NO. II, 33

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e. below, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6-e.

When in MODE 3, 4, or 5, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of at least the following factors:

1.

Reactor Coolant System boron concentration, 2.

CEA position, 3.

Reactor Coolant Sys. tem average temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 1.0% delta k/k at least once per 31 Effective Full Power Days (EFPD).

This comparison shall consider at least those factors stated in Specification 4.1.1.1.le., above.

The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPDs after each fuel loading.

WATERFORD - UNIT 3 3/4 1-2 AMENDMENT NO. 11

REACTlVITY CONTROL SYSTEMS SHUTDOWN MARGIN - ALL FULL LENGTH CEAS FULLY INSERTED LIMITING CONDITION FOR OPERATION l

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3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to that shown in Figure 3.1-0.

APPLICABILITY:

MODES 3, 4 and 5 with all full length CEAs fully inserted.

ACTION:

With the SHUTDOWN MARGIN less than that shown in Figure 3.1-0, immediately initiate and continue boration at greater than or equal to 40 gpm of a solu-tion containing greater than or equil to 1720 ppm boron or equivalent until the required SHUTOOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 With all full length CEAs fully inserted, the SHUT 00WN MARGIN shall be determined to be greater than or equal to that shown in Figure 3.1-0 at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1.

Reactor Coolant System boron concentration, 2.

CEA position, 3.

Reactor Coolant System average temperature, 4.

Fuel burnup based on gross thermal energy generation, l

5.

Xenon concentration,and 6.

Samarium concentration.

WATERFORD - UNIT 3 3/4 1-3 AMENDMENT NO. ZZ,33 D

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Figure 3.1-0 SMUTDOWN MARGIN AS A FUNCTION OF COLO LEG TEMPERATURE WATERFORD - UNIT 3 3/4 1-3a AMENDMENT NO. II,33

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ML20148G179

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