ML20211J019

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Summary of 860603 Meeting W/Util & C-E in Bethesda,Md to Discuss Fuel Cycle Design,Tech Spec Amends & Other Licensing Actions Needed to Support Cycle 2 Operations.Viewgraphs & Attendance List Encl
ML20211J019
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/10/1986
From: Joshua Wilson
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8606260153
Download: ML20211J019 (56)
v • d • e


Text

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[  % UNITED STATES

[f,..c*i NUCLEAR REGULATORY COMMISSION WASHINGTO N, D. C. 20555 E

5/  !- !

o.

%o '. ...Af JUN y g 1986 Docket No.: 50-382 LICENSEE: Louisiana Power and Light Company FACILITY: Waterford Steam Electric Station, Unit 3

SUBJECT:

SUMMARY

OF MEETING ON WATERFORD 3 RELOAD FOR CYCLE 2 A meeting was held in Bethesda, Maryland on June 3,1986 between the NRC staff and staff from LP&L and CE to discuss fuel cycle design, tech spec amendments and other licensing actions needed to support Cycle 2 operations at Waterford

3. A list of attendees at the meeting and their affiliation is attached as Enclosure I.

The meeting took the form of a briefing, where LP&L described to the staff the various submittals that would be necessary to permit receipt of fuel, fuel loading and startup from the refueling outage. The slides used in the briefing are attached as Enclosure II. Some of the salient points from the briefing are listed below:

At the present rate of burnup, LP&L will be ready to shut Waterford 3 down on 11/15/86 to begin a 48-day outage.

LP&L is currently scheduling receipt of fuel on 10/17/86, with fuel load to begin on 11/21/86, and startup to commence 1/1/87.

LP&L will be submitting the supporting documentation for fuel receipt, fuel loading and startup at least 90 days prior to each action.

The 92 fresh fuel assemblies to be used in Cycle 2 incorporate design changes that have been previously approved for use in other CE plants.

Neither CEA nor instrumentation replacement is scheduled.

LP&L does not plan on using any new unreviewed methodology in its reload analysis report.

LP&L anticipates submitting 31 technical specification changes. Most are related to the reload, some are the result of license conditions and some are the result of previous commitments.

LP&L does not plan to submit any tech spec changes which would be part of any tech spec improvement effort.

Whenever LP&L employs new methodology or design changes that have been previously approved by the NRC for use at other plants, clear reference will be made to those reviews to prevent unnecessary duplication of staff review effort and subsequent delay.

8606260153 860610 PDR ADOCK 0D000382 P PDR

t The staff advised LP&L to prioritize its submittals and establish " drop dead" dates for each action. Future meetings will be scheduled to resolve various detailed technical hard spots that may rise.

/~$~/

James li. Wilson, Project Manager

, PWR Project Directorate No. 7 Division of PWR Licensing-B

Enclosures:

As stated cc: See next page i

i i

l i

l PBD7 D7 JWils /es GWKnighton  :

6//d/86 //0 /86

__.___________.___._.._______________^_.______

. a .

Mr. G. W. Muench Louisiana Power & Light Company Waterford 3 cc:

W. Malcolm Stevenson, Esq. Regional Administrator, Region IV Monroe & Leman U.S. Nuclear Regulatory Commission 1432 Whitney Building Office of Executive Director New Orleans, Louisiana 70103 for Operations 611 Ryan Plaza Drive, Suite 1000 Mr. E. Blake Arlington, Texas 76011 Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Carole H. Burstein, Esq.

Washington, D.C. 20036 445 Walnut Street New Orleans, Louisiana 70118 Mr. Gary L. Groesch P. O. Box 791169 Mr. Charles B. Brinkman, Manager New Orleans, Louisiana 70179-1169 Washington Nuclear Operations Combustion Engineering, Inc.

Mr. F. J. Drummond 7910 Woodmont Avenue, Suite 1310 Project Manager - Nuclear Bethesda, Maryland 20814 Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Mr. K. W. Cook Nuclear Support and Licensing Manager Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Resident Inspector /Waterford NPS P. O. Box 822 Killona, Louisiana 70066 Mr. Jack Fager Middle South Services, Inc.

P. O. Box 61000 New Orleans, Louisiana 70161 Chairman Louisiana Public Service Commission One American Place, Suite 1630 Baton Rouge, Louisiana 70804 12

-_m Enclosure I LIST OF ATTENDEES AT JUNE 3, 1986 MEETING IN BETHESDA, MARYLAND TO DISCUSS ACTIVITIES NEEDED TO SUPPORT CYCLE 2 OPERATIONS AT j WATERFORD 3 i NRC-

+

J. Wilson

, G. Knighton C. Thomas l N. Lauben i D. Fieno 1 L. Kopp 1

J. Calvo I. Ahmed

! J. Luehman LP&L G. Muench K. Cook R. Nelson R. Murillo J

R. Wilkins K. Iyengar i

[E D. Earles I

R. Bandera S. Webster 1

O O ,

Enclosure II LOUISIANA POWER AND LIGHT COMPANY

\

l PRESENTATION TO NRC ON CYCLE 2 RELOAD L

JUNE 03, 1986 NS10212 1

. - _ - - = .

AGENDA CYCLE 2 RELOAD l 3 TOPIC PRESENTER TIME

1. INTRODUCTION R.J. Murillo 9:00 Meeting Objectives  !

Agenda ,

Reload Target Dates Questions and Answers

2. LICENSING ACTIVITIES R.J. Murillo 9:15 Technical Specifications Analysis Methods

,I Reload Analysis Report Licensing Commitments i

j 3. CYCLE 1 OPERATING HISTORY R.M. Wilkins 9:30 l

  • Major outages since commercial operation l

Capacity factor

  • Planned shutdown window l

j 4. CYCLE 2 GENERAL DESCRIPTION R.M. Wilkins 9:45 1

j

  • Fresh fuel assembly types and quantity Loading pattern CEA and in-core instrumentation status l

4 l5. CYCLE 2 NUCLEAR DESIGN R.M. Wilkins 10:00

  • Fuel management 1

i

  • Methodology i 6. FRESH FUEL DESIGN R.M. Wilkins 10:15 .

t Hechanical design I -Shoulder gap

-Guide tube sleeve design Shoulder gap adequacy i

1

! 7.

  • THERMAL HYDRAULIC DESIGN R.M. Wilkins 10:45 Statistical combination of uncertainties
  • Methodology i.

1 NS41077 2

___ _ . _ _ =_ , _ m... _ - _ - . _ _ . __ _ _. _ _ _ _ _ _ _

!. AGENDA I CYCLE 2 RELOAD (Continued)

. TOPIC PRESENTER TIME i
8. R.M. Wilkins

~

TRANSIENT ANALYSES 11:00 ECCS Analysis

(

Non-LOCA Analysis

9. REACTOR PROTECTION SYSTEM R.M. Wilkins 11:15  ;

1

-CPC software modifications j -CPC improvement program

-Reload data block i
10. STARTUP TEST PROGRAM 11:45 Fast Power Ascension Program Control Rod Worth Measurement

{ 11. LUNCH 12:00 - 1:00 j 12. TECHNICAL SPECIFICATION CHANGES R.M. Wilkins 1:00

+

Fuel enrichment limits

+

Boration control i -

Shutdown margin Moderator temperature coefficient.

Axial shape index CEA PDIL Safety limits, setpoints and margins Reactor vessel level monitoring system j -

RCS Flow Rate 1

13. LICENSE CONDITIONS R.J. Murillo 2
00 j
  • Control Room Smoke Detectors. (2.C.9.d)

Spurious Signal Analysis Modifications (2.C.9.e)

LCP-43 Neutron Flux Indication (2.C.9.f)

Containment Isolation Valves (Attach. 1, Item C)

+

Axial Fuel Growth (2.C.7)

{

+ Broad Range Toxic Gas Detectors (2.C.4) 1 l

14. LICENSING COMMITMENTS .

R.J. Murillo 2:30.

Commitment Profile Control Systems Single Failure Study Reactor Vessel Level Monitoring, HJTC Control Room Envelope T.S. 4.7.6

j

+

RCS Pressure Indication i

l i 3

AGENDA' '

CYCLE 2 RELOAD .

(Continued)

TOPIC PRESENTER TIME

15. LICENSING SCHEDULE R.J. Murillo 3:00 Reload Analysis Report Licensing Issue Submittals Technical Specifications
16. QUESTIONS AND ANSWERS All 3:30 4

'6 O 9 MEETING OBJECTIVES 0 PLANNING AND COORDINATION RESOURCES SCHEDULE O CYCLE 2 RELOAD TECHNICAL BASIS MINIMAL DESIGN CHANGES APPROVED ANALYSIS METHODS 0 CYCLE 2 RELOAD LICENSING BASIS NORMAL LICENSING SUBMITTALS IDENTIFIED RESOLUTION OF ISSUES 5

CYCLE 2 RELOAD TARGET DATES 0 TARGET FUEL SHIPMENT

- OCTOBER 17, 1986 0 TARGET SHUTDOWN

- NOVEMBER 15, 1986 0 TARGET FUEL LOAD

- NOVEMBER 21, 1986 0 TARGET STARTUP

- JANUARY 01, 1987 6

TECHNICAL SPECIFICATIONS 0 THIRTY-ONE (31) NEW OR CHANGED T.S.

RELOAD LICENSE CONDITIONS COMMITMENTS 0 T. S. CHANGES PHASED SUBMITTALS FUEL RECEIPT FUEL LOAD START-UP l

ANALYSES NRC REVIEW 7 .

ANALYSIS METHODS i

0 NEW METHODOLOGY o CPC RELOAD DATA BLOCK, CEN-330 o CE AXIAL POWER SHAPE, LB-LOCA 0 NRC APPROVED METHODS FOR CYCLE 2 o SCU FOR CPC a COLSS o CPC IMPROVEMENT PROGRAM 8

O 9 RELOAD ANALYSIS REPORT l

(RAR)

/

0 TYPICAL 3410 PLANT LICENSE SUBMITTAL 0 TYPICAL SAR CHAPTER 15 ANALYSES 0 T. S. INCORPORATED BY REFERENCE l

t I

l t.

9

p .

LICENSING COMMITMENTS O RELOAD COMMITMENTS IDENTIFIED, ASSIGNED, AND SCHEDULED 0 PRIMARY AND SECONDARY RESPONSIBILITY IDENTIFIED O CONTINUING REVIEW AND EVALUATION, MONTHLY REPORTS l

l I

10

WATERFORD 3 CYCLE 1 OPERATING HISTORY LOW POWER OPERATING LICENSE 12/18/84 FULL POWER OPERATING LICENSE 03/16/85 COMMERCIAL OPERATION 09/24/85 MAJOR OUTAGES 10/2-10/85 REPLACE REACTOR COOLANT PUMP SEALS 12/6-17/85 REPLACE REACTOR COOLANT PUMP SEAL S 03/7-30/86 MAINTENANCE / TECH. SPEC SURVEILLANCE OUTAGE CAPACITY FACTOR THROUGH MAY, 1986 76%

PLANNED SHUTDOWN FOR END OF CYCLE 1 TARGET DATE: 11/15/86 BURNUP WINDOW: 13.4 - 14.4 GWD/MTU 11

s WATERFORD 3 .

CYCLE 2 DESIGN

-GENERAL DESCRIPTION

-NUCLEAR DESIGN

-MECHANICAL DESIGN

-THERMAL HYDRAULIC DESIGN

-TRANSIENT ANALYSIS

-CPC MODIFICATIONS 12 '

WATERFORD 3 CYCLE 2 BATCH D FUEL ASSEMBLIES .

XX XX 1 XX >

XX X X '

X X.

XX XX XX XXi X '- X X X . X X '

X X Y X X X X X X X XX XX XX XX-XX XX __

X X X --

X .__ i X X X X XX XX XX XX XX XX __.

X X X X X X X X X X X X X X X ;X -

XX 'X:X XX XX -

X X -X X XX -

XXi ;XX XX 0 0*

(.0 shims) (4 shims) 3.90 with 3.40 w/o 3.90 wi th 3.40 w/o IXX XX' lXX XX X X E R

.l . _

l ~ ~ ~ ---

E E _.__ l _. _-~~

I ._ _ .

l - --

l l __ ...

I Q G l 3 3 X X; XJ c x' iXX LXX XX XIX, D/ OX (4 shims) (8 snims) 3.40 with 2. 78 w/o l 3.40 with 2.78 w/o w a

WATERFORD 3 CYCLE 2 FRESH FUEL DESIGN

_D* _DL JL TOTAL

_l)_

12 2ri 32. W .

74 NUMBER OF ASSFMBLIES fMRICHMENTs (w/O 11-235) 3.40 (216) 3 90 (1881) .3 90 (180) 3.fio (220) tilGH ZONE PINS ---

3 4Q (52) 2 78 (12) 2 78 (12) l_OW ZONE PINS 3 40 (52) 3 37 3 37 3 53 3 79 3 79 AsSEMaty AVERAGF 4 4 8 0

NIMRER OF SHIMS PER ASSEMBLY --

--- 019 019. 019 SHIM STRENGTH (GM B-10/IN) 9

') l E

14

WATERFORD 3 CYCLE 2 ,

1 FUEL LOADING PATTERN  :

l

. i e S D S

~~

3 4 G 7 C I I IX B 6 T to Ii 11 13 8 3r C C C+ 31 i+ IS 16 17 te of 2a 3 ,

De C 24 3 D/ 3 2 22. 23 24 2r 26 27 2s C ps C pg 3 .c 3 DX Ty Jo 71 JZ 33 34 35 J6

% C IX 3 D/

/ 3 E s, u .n u +z

  • i +3 e

+g D C 3 C S Dy C. DX 3 u o w e r, r, s2. rs

,. Dy C+ DI S DI C. C+ C+

D rs ss n is sr a st <=

3 D/ 3 TX 3 TX C+ .B 15

-. - - . - - . - . - .. .- -. - . = . - - .

WATERFORD 3 CYCLE 2 CORE COMPONENT STATUS NO CEA REPLACEMENT NO IN-CORE INSTRUMENTATION REPLACEMENT i

I 4

d 9

1 16'

i t WATERFORD 3 CYCLE 2 .

NUCLEAR DESIGN 18-MONTH CYCLE DESIGN ENERGY 14,750 MWD /MTU 390 EFPD IN-IN-0UT FUEL MANAGEMENT SAME CORE POWER LEVEL (3390 MWTH) AND BASE LOADED OPERATION AS IN CYCLE 1 AUGMENTATION FACTORS ELIMINATED PHYSICS METHODOLOGY ROCS-DIT AND MC NO UNREVIEWED METHODOLOGY CHANGES

. 17

WATERFORD 3 CYCLE 2 ESTIMATED POWER DISTRIBUTIONS B D

.38 .75 ,

.46 .84 C D D DX B

.48 .99 1.19 1.13 .86

.51 .90- 1.06 1.16 .92 B D* C C C+ D/

.43 1.13- 1.14 1.17 1.08 1.32

.50 1.10 1.02 1.04 1.02 1.25 D* C DX B D/ B 1.12 1.09 1.29 .96 1.31 .99 1.11 1.05 1.26 .95 1.23 .98 DX B C B DX 1,29 .91 1.01 .94 1.23 1.29 .95 1.02 .97 1.26 D/ B D/ B 1.20 .89 1.24 .92 1.22 .95 1.24 .98 DX C. DX

~

1.18 .99 1.16 1.25 1.03 1.25 BATCH C+ C+

BOC-2 .89 .86 EOC .98 .97 B

ASSEMBLY RELATIVE POWER DENSITY .68 (HOT FULL POWER, EQUILIBRIUM .83 UNRODDED CONDITIONS) 18

WATERFORD 3 CYCLE 2 CORE PHYSICS CHARACTERISTICS

  • MAXIMUM RADIAL PLANAR PEAKING FACTOR F xy = 1.58 (AR0,HFP)

MODERATOR TEMPERATURE COEFFICIENT 4

MTC = +0.33 x 10-46p/*F (B0C,HZP)

MTC = -0.12 x 10-4 a /*F (BOC,HFP)

MTC = -2. 55 x 10-43 ,joF (EG:,FFP)

CRITICAL BORON CONCENTRATION CBC = 1180 PPM (BOC,HFP,AR0)

INVERSE BORON WORTH IBW = 107 PPM /% ap (B0C,HFP)

IBW = 85 PPM /% ap (EOC,HFP)

CEA SCRAM REACTIVITY WORTH WORTH = -11.0% ap (BOC,HFP,ARI)

WORTH = -9.1 % ap (B0C,HFP,N-1)

  • BEST ESTIMATE, NO UNCERTAINTIES APPLIED l 19 i .. ._. ._ .

l WATERFORD 3 CYCLE'2 FUEL MECHANICAL DESIGN GENERAL DESIGN FEATURES BATCH D FUEL MECHANICAL DESIGN IS ESSENTIALLY THE SAME AS BATCHES A-C 16 x 16 FUEL ASSEMBLY 150 INCHES ACTIVE FUEL LENGTH 11 SPACER GRIDS TWO BATCH D MECHANICAL DESIGN CHANGES

-GUIDE TUBE SLEEVE DESIGN

-FUEL ASSEMBLY SHOULDER GAP 1

9 l

20

ALIGNMENT POST

m. ,,

UPPER END'f I I 1 issWWE FITTING ' j l l @y

f3@d@,=

i

"; '= e mee =

CEA W t E GUIDE TUBE Tu tn=4._ 176.6" 5MTM ASSEMBLY 'c6cbsidisdodoil OVERALL TOP VlB4

a FUEL ROD crew.n s 0000000205000c00 a:::::::t p /

GRID 150" ACTIVE FUEL LENGTH 8888888888888888 88 m 8888 88 ggk%g g gg .

88888 8888: 88888 gj8 8 E.00@8 888jj 88@!!!!88.8!!

si88a in6sininin5 sin 6s

- --'--~

u BOTTOM VIEW

^

LOWER >

END FITTING _ _ .

AMENDMENT NO 33 (9/83) 9#'

LOUISIANA POWER & LIGHT CO. FUEL ASSEMBLY 4.2 8 Waterford Steam

. . c . . ..

4 9 r

WATERFORD 3 CYCLE 2 GUIDE TUBE SLEEVE DESIGN ALL FUEL ASSEMBLIES PLACED IN CEA LOCATIONS IN CYCLE 2 WILL HAVE STAINLESS STEEL SLEEVES INSTALLED IN THE GUIDE TUBES BATCH D SLEEVE DESIGN

-SLEEVES INSTALLED COMPLETELY WITHIN THE GUIDE TUBES

-SLEEVE EXPANDED ALONG ITS ENTIRE LENGTH

-ELIMINATES NEED FOR VENT HOLES

-FACILITATES FUEL BUNDLE RECONSTITUTION

-NRC APPROVAL IN LETTER DATED 09-07-84 1

I

i. gg

- . . . _m _ _ _ _ _ _ _ . . _ . __ ._ __

COMPARISON OF WATERFORD-3 ORIGINAL CORE FUEL BUNDLES TO BATCil D FUEL BUNDLES I 1 .

/ y f*" ]  % .

fuel Assembly I.esigth increased ,

, Change 5 i

l ( ,, , ,  ; Recessed Holddown ,

{_ i 3 , J Plate (0.300")

J' 1 si l

ll ll l Il la I gi Il !l ll l' 3 l

Change 4 I ' '

I Il 18 g $ Shorter Posts (0.700")

i I

,a 5.850" 5.650" l

,! l 8l l l 1l 1 ll lii liI lI el I i ils il e, li i

ll Ii, ,

'3: 1 l s' Change 3 I a '<

h Thinner Flow Plate (0.400")

v l $(

u i Change 2 I,onger Guide Tubes (0.900")

1.322" 2.302"

' / l 1 Change 1 ff , f kf ' - - - -- -- - -'

Shorter Fuel Rods (0.150")

s u . ..N . .- a w m A A >

ORIGINAL CORE BATCH D 23

i WATERFORD 3 CYCLE 2 SHOULDER GAP ADEQUACY MEASURED DATA AVAILABLE FROM SEVERAL CYCLES i AT OTHER PLANTS FOR 16 x 16 FUEL RESULTS OF MEASUREMENTS DEMONSTRATE ACCEPTABILITY i 0F SHOULDER GAP FOR BURNUP LEVELS TO BE j ACHIEVED IN CYCLE 2 NO SHOULDER GAP MEASUREMENTS TO BE PERFORMED 4

DURING FIRST REFUELING OUTAGE 1

' f

}

2I4 i

1 l

l WATERFORD 3 CYCLE 2 THERMAL' HYDRAULIC DESIGN STEADY STATE DNBR METHODOLOGY

-TORC

-CETOP

-CE-1 CRITICAL HEAT FLUX CORRELATION STATISTICAL COMBINATION OF UNCERTAINTIES

-UNCERTAINTIES ASSOCIATED WITH CHF DATABASE

-UNCERTAINTIES ASSOCIATED WITH SYSTEM PARAMETERS

-MEASUREMENT UNCERTAINTIES N0 UNREVIEWED METHODOLOGY CHANGES E

WATERFORD 3 CYCLE 2 TRANSIENT ANALYSIS ECCS PERFORMANCE - LARGE BREAK LOCA

-SAME MODEL AS CURRENT ACCEPTED ANALYSIS NUREG 0630 NEW AXIAL SHAPE METHOD

-WILL EMPLOY FATES 3 FISSION GAS RELEASE MODEL NON-LOCA TRANSIENT ANALYSES

-INCORPORATE CPC IMPROVEMENT PROGRAM SOFTWARE 4

CHANGES INTO ANALYSES

-N0 UNREVIEWED METHODS -

-ALL FSAR CHAPTER 15 EVENTS WILL MEET NRC ACCEPTANCE CRITERIA, ALTHOUGH SOME MAY EXCEED THE CONSEQUENCES OF THE CYCLE 1 EVENTS l

1 l

l 1

26

l I

i WATERFORD 3 CYCLE 2 CPC MODIFICATIONS PROGRAM GOALS REDUCE UNNECESSARY PLANT TRIPS

-AVOID TRANSIENTS CAUSED BY UNNECESSARY PLANT TRIPS

' IMPROVE PLANT AVAILABILITY AVOID FUTURE CPC SOFTWARE CHANGES 1 -REDUCE RELOAD EFFORT, CALENDAR TIME AND NEED FOR NRC REVIEWS SIMPLIFY RELOAD ANALYSES 4

-REDUCE RELOAD EFFORT AND CALENDAR TIME MAINTAIN MARGINS TO SAFETY

, - - - < e

- , - . - - , e.

WATERFORD 3 CYCLE 2 CPC MODIFICATIONS CPC OVERSIGHT COMMITTEE -- COMPOSED OF REPRESENTATIVES FROM FOUR DIGITAL PLANT UTILITIES WITH C-E AS THE TECHNICAL CONSULTANT l -

OPTIMIZATION OF CPC/CEAC SOFTWARE FOR RELOADS

  • 1 -

CEAC DESENSITIZATION T0. SPURIOUS SIGNALS

  • RELOAD DATA BLOCK +
  • DETAILS PRESENTED TO NRC IN CEN-308-P (AUGUST, 1985)

AND CEN-310-P (OCTOBER,-1985) AND APPROVED IN NRC LETTER DAlED MARCH 12, 1986.

+ DETAILS PRESENTED TO NRC IN CEN-323-P (JANUARY, 1986)

AND CEN-330-P (MAY, 1986) l I

28

I J

WATERFORD 3 CYCLE 2 STARTUP TEST PROGRAM FAST POWER ASCENSION PROGRAM

-REDUCE CRITICAL PATH TIME ,

-MAINTAIN STARTUP TEST OBJECTIVES

-MONITORING OF COLSS/CPC PARAMETERS AS POWER INCREASED TO 70% AND 95% POWER TEST PLATEAUS

-PROGRAM DEMONSTRATED ON SIMILAR 3410MW' PLANT CONTROL R0D WORTH MEASUREMENT

-CEA EXCHANGE TECHNIQUE (CEN-319)

-APPROVED BY NRC 1

29 -

l WATERFORD 3 CYCLE 2 PROPOSED TECH. SPEC. CHANGES FUEL ENRICHMENT LIMITS

-TECH SPEC 5.3.1

-ENRICHMENT LIMIT INCREASE FROM 3.70 W/0 TO .

13.85 W/0 4tss B0 RATION CONTROL

-TECH. SPECS. 3.1.1.1 3.1.1.2 -

3.1.2.7 3.1.2.8 3.5.1 3.5.4 3.9.1 3.10.1

-INCREASED CORE REACTIVITY AT B0C RAISES CRITICAL BORON CONCENTRATION

-POTENTIAL INCREASE MINIMUM' REFUELING BORON CONCENTRATION i

i l

30 _ _ _ .

WATERFORD 3 CYCLE 2 PROPOSED TECH. SPEC CHANGES SHUTDOWN MARGIN

~

-TECH. SPECS. 3.1.1.1 3.1.1.2 3.1.2.2 1

3 . 1 . 2 . 11 3.1.2.6 3.1.2.8 3.1.2.9

-ANALYSIS RESULTS MAY RESULT IN INCREASES TO '

SHUTDOWN MARGIN

-IMPROVED METHODS MAY REDUCE SHUTDOWN MARGINS IN SUBCRITICAL MODES' MODERATOR TEMPERATURE COEFFICIENT (MTC)

-TECH SPEC. 3.1.1.3

-HIGHER INITIAL BORON CONCENTRATION MAKES THE

BOC MTC MORE POSITIVE

-HIGHER FUEL BURNUP MAKES E0C MTC MORE NEGATIVE AXIAL SHAPE INDEX (ASI)

-TECH. SPEC. 3.2.7

-ASI LIMITS NARROWER d

31

WATERFORD 3 CYCLE 2 PROPOSED TECH SPEC. CHANGES

- CEA POWER DEPENDENT INSERTION LIMITS (PDIL)

-TECH SPECS. 3.1.3.1 3.1.3.6 3.1.3.7 3.10.2

-MAKE PDIL FOR FULL LENGTH CEA MORE RESTRICTIVE

-ADD PDIL FIGURE FOR PLCEA

-ADD FIGURE FOR CORE POWER REDUCTION VS. TIME FOR CEA DROP

-ADD-TECH. SPEC. 3.1.3.7 TO SPECIAL TEST EXCEPTION

. SAFETY LIMITS, SETPOINTS, AND MARGINS

-TECH. SPECS. 2.1.1.1 2.1.1.2 2.2.1 3.2.1 3.2.4 3.3.1

-IMPLEMENTATION OF SCU METHODOLOGY

-CHANGES TO SETPOINTS BASED ON CYCLE 2 ANALYSES

-CHANGES TO CEAC INOPERABLE AND COLSS OUT-0F-SERVICE MARGINS BASED ON CYCLE 2 ANALYSES

-PROVIDE CONSISTENT ACTION AND SURVEILLANCE REQUIREMENTS 32

b o

! WATERFORD 3 CYCLE 2 PROPOSED TECH. SPEC. CHANGES l

4 .

1

RCS FLOW RATE 4

-TECH. SPEC. 3.2.5

! -CLARIFY WORDING 0F RCS FLOW RATE 1

i REACTOR VESSEL LEVEL MONITORING SYSTEM (RVLMS) i -TECH. SPEC. 3.3.3.6  ;

i

-IMPLEMENT NEW TECH. SPEC. PER LICENSE COMMITMENT  :

I p

3

  • r i

~

i  :

4 i

J I

e

't 33

i LICENSE CONDITION

, CONTROL ROOM SM0KE DETECTORS l 0 REGULATORY BASIS i

LICENSE CONDITION 2.C.9.D SSER 8 I - APPENDIX R AUDIT, INSPECTION 84-20 i

I 4

0 STATEMENT OF REQUIREMENT PROVIDE SMOKE DETECTORS IN CONTROL ROOM MAIN PANELS INSTALL TO MEET NFPA 72E i .

O STATUS -

- BATTERY POWERED SMOKE DETECTORS, INTERIM' MEASURE j i DESIGN WORK UNDERWAY i

4

-- MODIFICATION SCHEDULED SEPTEMBER, 1986  :

e .

O ASSESSMENT-T. S. CHANGE TABLE.3.3.3.8' REQUIRED COMPLIANCE WITH REGULATORY' BASIS EXPECTED 34 .

1 LICENSE CONDITION SPURIOUS SIGNAL ANAL.YSIS MODIFICATION l

4 0 REGULATORY BASIS 4

LICENSE CONDITION 2.C.9.E '

l SSER 8

- APPENDIX R AUDIT, INSPECTION 84-20 3 0 STATEMENT OF REQUIREMENT j COMPLETE MODIFICATIONS FROM SSA PRIOR STARTUP '

j -

REVISE PROCEDURES CONSISTENT WITH MODIFICATIONS l 0 STATUS 1

I ISOLATION CIRCUlTS IDENTIFIED, 75  !

-- EBASCO SMP MID JULY, 1986 i .0 ASSESSMENT COMPLIANCE WITH REGULATORY BASIS EXPECTED < .

1 l

l i

I 35 w- , owSH-.--- y -.p =+psq.m , -. t, - - .g.' < .e4-t w.: y .

nyw is.-%- q e.o4..%,+,yw . g ,p . ,p_y--es.w w . ,.-n. -

4 y 9c- .p,,yg gm

LICENSE CONDITION LCP-43 NEUTRON FLUX INDICATION 0 REGULATORY BASIS LICENSE CONDITION 2 C.9.F SSER 8 i

- APPENDIX R AUDIT, INSPECTION 84-20 O STATEMENT OF REQUIREMENT PROVIDE NEUTRON FLUX INDICATION AT LCP-43 PRIOR STARTUP INDICATION ELECTRICALLY INDEPENDENT CONTROL ROOM AND CABLE VAULT O STATUS.

i -

'SMP IN APPROVAL CYCLE f

MODIFICATIONS IDENTIFIED O ASSESSMENT .

SIGN!FICANT PORTION HARDWARE CHANGER EXPECTED TO'BE COMPLETED PRIOR OUTAGE COMPLIANCE WITH REGULATORY BASIS EXPECTED 36

.- . y 4

LICENSING CONDITION ,

-CONTAINMENT ISOLATION VALVES L

0 REGULATORY BASIS l - License Condition NPF-26, Attachment 1, Item C 1 -

NPF-38 did not alter wording-4 O STATEMENT OF. REQUIREMENT Continuous, direct position indication in CR.for l containment isolation valves CVR-401A & CVR-401B (penetrations 53-a 65) l

- Completion prior to Startup i i

0 STATUS-n L -

Station Modification Request-(SMP) - 631 i . issued to install valves during outage ,

I 0 ASSESSMENT

-Compliance with Regulatory. Basis expected i 1

37-1 1

1

LICENSING CONDITION AXIAL FUEL GROWTH 0 REGULATORY BASIS

- LICENSE CONDITION 2.C,7

- SSER 5, SECTION 4.2 0 STATEMENT OF REQUIREMENT PROVIDE REPORT To DEMONSTRATE FEA HAVE SUFFICIENT SHOULDER GAP, OR IMPLEMENT MODIFIED FEA DESIGN 0 STATUS AVAILABLE DATA DEMONSTRATES ACCEPTABLE DESIGN 0 ASSESSMENT LP&L PROVIDE REPORT PER LICENSE CONDITION

- CEN-309, CEN-332 38

e LICENSING CONDITION BROAD RANGE T0XIC-GAS DETECTION SYSTEM (BRTGDS) 0 REGULATORY BASIS

' - LICENSE CONDITION 2 C,4 SSER 6, SECTION 2.2~1 0 STATEMENT OF REQUIREMENT OPERABLE BRTGDS PRIOR TO STARTUP PROPOSE T.S. PRIOR TO STARTUP 0 STATUS I -

DESIGN COMPLETE SYSTEM IN PLACE 201 ANALYZER LAMP DEGRADATION SENSITIVITY CALIBRATION EXPERIENCE REQUIRED i

0 ASSESSMENT LP&L MAY NEED TO JUSTIFY LOWER POTENTIAL LAMP LP&L MAY NEED TO ACQUIRE SENSITIVITY EXPERIENCE FOR CALIBRATION / PROGRAMMING

39

COMMITMENT PROFILE O 152 CYCLE 2 RELOAD COMMITMENTS 3 INVOLVE CHANGES / DEVELOPMENT OF TECHNICAL SPECIFICATIONS 0 PROVIDE FOR A BROAD RANGE T0XIC GAS DETECTION SYSTEM. (A08212) 0 SPECIFY A LIMIT ON ALLOWABLE MAKEUP AIR FOR THE CONTROL ROOM. (A0836) 0 DEVELOP TECH SPECS FOR LCO AND SURVEILLANCE REQUIREMENTS ON APS (A08319) 5 REQUIRE PROCEDURE CHANGES (NON-HED) 0 IMPLEMENT PROCEDURES TO ADDRESS THE EFFECTS OF POTENTIAL FIRE INDUCED SPURIOUS OPERATIONS, (A08323) 0 DEVELOP HJTC INSTRUCTIONS AND INCORPORATE INTO EMERGENCY PROCEDURES, (2) (A08194 & A08320) 0 DEVELOP PROCEDURES FOR CONTROL OF HEAVY LOADS, (2)

(A08517 & A08519) 7 REQUIRE HARDWARE CHANGES (NON-HED) 0 INSTALL CONTINUOUS AND DIRECT INDICATION FOR CONTAINMENT ISOLATION VALVES. (A08343) 0 INSTALL 0-RINGS FOR SECONDARY SEALING OF BORG WARNER ACTUATORS. (A09364) 0 INSTALLATION OF SUPPLEMENTARY FUEL POOL HEAT EXCHANGER. (A08189) 0 INSTALLATION OF (2) TRIAXIAL PEAK ACCELER0 GRAPHS, (A08516) 0 INSTALLATION OF SM0KE DETECTORS FOR CONTROL ROOM CABINETS / CONSOLES, (2) (A08278 & A08328)

O PROVIDE MANUAL DELUGE SYSTEM FOR EACH' BANK OF CHARCOAL FILTERS, (A08314) 40

COMMITMENT PROFILE (CONTINUED) 112 HEDS 0 MISSING, INCORRECT OR INAPPROPRIATE LABELS 0 INCORRECT POSITIONING OF LABELS 0 INCORRECT ABBREVIATIONS 0 INCORRECT SCALING OF METERS 0 INCORRECT SCALE PAPER FOR METERS 0 INCORRECT POSITIONING / MOUNTING OF CONTROL ROOM CLOCK 0 INCORRECT POSITIONIN0/ MOUNTING OF CONTROL ROOM TELEPHONE O INADEQUATE ALARM /PA SPEAKER SYSTEM 0 INADEQUATE COLOR CONTRAST OF CONTROL PANELS 0 VARIOUS HED RELATED PROCEDURE CHANGES (5) 0 ACQUISITION OF EQUIPMENT AND SUPPLIES 25 REMAINDER COMMITMENTS ADDRESS 0 MAINTENANCE O TRAINING l i

0 INSPECTION, INVESTIGATION-AND EVALUATION OF VARIOUS PLANT AREAS, 41

LICENSING COMMITMENTS CONTROL SYSTEMS SINGLE FAILURE STUDY 0 REGULATORY BASIS IE BULLETIN 79-27 USI A-47

- SER 7.1; SSER 1, 7.7; SSER 6, 7.1.2; SSER 8, 7.7.6 0 STATEMENT OF REQUIREMENT PROVIDE TO NRC SINGLE FAILURE STUDY OF CONTROL SYSTEMS DEMONSTRATE RESULTS BOUNDED BY FSAR CHAPTER 15 EVENTS, OR CORRECT DEFICIENCIES PRIOR'TO STARTUP O STATUS STUDY COMPLETED FAULT TREES BEING VALIDATED BY LP&L i ALL RESULTS BOUNDED BY FSAR EVENTS j NO DEFICIENCIES IDENTIFIED )

l 0 ASSESSMENT-  ;

LP&L SUBMITTAL WILL DEMONSTRATE COMPLIANCE WITH REGULATORY BASIS i

42

a w

LICENSING COMMITMENTS REACTOR VESSEL LEVEL MONITORING s..

(HJTC) '

s

~

0 REGULATORY BASIS .

! - NUREG 0737, 11.F.2 4-

- SSER 5, SECTION 22, ITEM ll.F.2 4

- LPal LETTER W3P83~-0847, MARCH 25, 1983 ,

i i

0 STATEMENT OF REQUIREMENT 4

,s s.

INCORPORATE INSTRUCTIOSS ;0N USE OF HJTC INTO EMERGENCY PROCEDURES PRIOR TO STARTUP

~

t APPROVE T.S. - FOR HJTC PRIORTO STARTUP 0 STATUS E0PS IN FINAL REVIEW

- T,S. CHNi4GE REQUIRED \ a  !

( '

~

i. i
L
,. -!

N  !

O ASSESSMENT  :,~ i-

+  ;.

. COMPLIANCE WITH REGillATORY' BASIS EXPECTED.

r?'1 m .

, r; y

j I e

, 43- l u _. .1_. -- . . -

4 LICENSING COMMITMENTS CONTROL ROOM ENVELOPE T,S, 4,7,6 0 REGULATORY BASIS

- LP&L LETTER W3P85-0592, DATED MARCH 6, 1985

- LP&L LETTER W3P85-3154, DATED JANUARY 24, 1986

}

0 STATEMENT OF REQUIREMENT REEVALUATE T0xIc CHEMICAL RELEASE-PROPOSE T.S. 4.7,6 MAKE-UP FLOW RATE 0 STATUS LP&L JUSTIFIES NO NEED FOR T.S.

UNDER-REVIEW BY NRC

LICENSING COMMITMENTS AUXILIARY PRESSURIZER SPRAY O REGULATORY BASIS LICENSE-CONDITION 2.C.12

- SSER 8, SECTION 5.4.3

- LP8L LETTER W3P84-1492, MAY 29, 1984 0 STATEMENT OF REQUIREMENT DEVELOP T.S. FOR APS 0 STATUS

- NRC LETTER APRIL 22, 1986, LICENSE CONDITION SATISFIED

- APS CAN PERFORM NECESSARY DEPRESSURIZATION, T.R. EVENT 0 ASSESSMENT LP8L WILL JUSTIFY NO NEED FOR T.S.

45

LICENSING COMMITMENTS RCS PRESSURE RANGE INDICATION O REGULATORY BASIS

- RG 1,97, R2 LP8L LETTER W3P84-3454 0 STATEMENT OF REQUIREMENT PRIOR TO STARTUP:

A. PROVIDE _ COMMITMENT TO INSTALL CATEGORY I INSTRUMENTATION FOR RCS PRESSURE RANGE INDICATION CONSISTENT WITH RG 1.97, R2 (0-4000 PSIG); OR '

B. PROVIDE ACCEPTABLE JUSTIFICATION FOR MAINTAINING RCS PRESSURE INDICATION IN THE RANGE 0-3000 PSIG 0 STATUS EVALUATING TO DETERMINE ACCEPTABLE APPROACH BASED ON ATWS 10CFR50,62 RESOLUTION 0 ASSESSMENT LICENSING SUBMITTAL WOULD BE PROVIDED IF LP8L

! POSITION IS TO JUSTIFY CURRENT RANGE (0-3000)

'46

r.YCLE 2 RELOAD SCHEDULE RELOAD At!ALYSIS PEPORT -

PART A *

(SHIP FUEL; 10/17/86)

1. INTRODUCTION 8

SUMMARY

2. OPERATING HISTORY OF REFERENCE CYCLE *

(LOAD FUEL; 11/21/86)

3. GENERAL DESCRIPTION
4. FUEL SYSTEM DESIGN
5.  ?!UCLEAR DESIGN
6. THERMAL HYDRAULIC DESIGN
11. START-UP  !

l PART B l@

.s 7.

8.

TRANSIENT ANALYSES ECCS ANALYSES PART A (14 WKS.) !k iH

9. RPS 6/01/86) l y, .

10.

12.

TECHNICAL SPECIFICATIONS REFERENCES PART B (90 DAYS) l$

l $

(10/01/86) lB e, co s

LEGEND l LEFT DATE: NRC SUBMITTAL RIGHT DATE: flRC APPROVAL

, , , , i . . , ,

06/01/86 07/01/E6 08/01/86 09/01/86 10/01/86 11/01/86 12/01/PE 01/01/E7 02/01/87 47

o c CYCLE 2.R_El.0 R SCHEDUIE e (LICENSING ISSUE SUBMITTALS)

' LEGEND ,

LEFT DATE: NRC SUBMITTAL RIGHT DATE: HRC Approval

(7/15/86) (11/01/86)

AX. FUEL l p,

. GROWTH l?

,o (8/01/86) (9/01/86) l> .i i o LB-LOCA AXIAL POWER SilAPE l ;'. -

,0 (7/01/86) (10/01/86) l4 l5 CPC RELOAD DATA BLOCK l b; 5/21/86) (12/01/86)  ! .

. .l lRCS PRESSURE INDICATI0Fl l

.L_____________________J l t (8/01/86) (l0/01/86) 8 06/01/86 07/01/8E 08/01/86 09/0 /86 10/01/86 11/01/86 12/01/86 0$[01 8[ 02/01/87

. II8

. v ,

TECHNICAL SPECIFICATIONS SUBMITTAL GROUP A -

Required Prior to Fuel Receipt (10/17/86)

(2) NRC Submittal 7/01/86 NRC Approval 10/01/86 NRC Review Time 90 days GROUP B -

Required Prior to Fuel Load (11/21/86)

(2) NRC Submittal 8/21/86 NRC Approval 11/21/86 NRC Review Time 90 days GROUP C - - Required Prior to Mode 5 (12/25/86)

< (5) NRC Submittal 9/25/86 NRC Approval 12/25/86 j NRC Review Time 90 days GROUP D -

Required Prior to Startup (01/01/87)

(6) NRC Submittal 10/01/86 NRC Approval 01/01/87 NRC Review Time 90 days GROUP E -

Required Prior to Startup (01/01/87)

(7) NRC Submittal 8/01/86 NRC Approval 12/15/86 NRC Review Time 18 weeks GROUP F -

Required Prior to Startup (01/01/87)

(6) NRC Submittal 9/01/86 NRC Approval 12/15/86 NRC Review Time 14 weeks GROUP G -

Required Prior to Startup (1) NRC Submittal 12/22/85 NRC Approval 6/22/86 NRC Review Time 6 months GROUP H -

Non-Reload, No Schedule Constraint (01/01/87)

(8) NRC Submittal, Staggered NRC Review Time, Open 7

. NS10213 49

- . ._n.-

POTEXTI.AL .TE. C.HN IC. AL. .S. PE.CI FirA.T.IC. .S C.;AN. GF_.S.

2

(~ 7/nl/lii.E 7 t/25/86) (lojul/ W (1) GM' HIP A (10/08/46) (2) GRfX1P R ( 8/21/86 I ~ ~ ~ ~(7)

_(81/23/86)

CRf%IP C (l_2/25/_8J L (5) CRt41P p (06/01/87) _ _ .

TEill SITC NATHkE of TECH SPEC NATimE OF 1ECH SPEC MATtmE OF TECH SPEC NATIVE OF SECTlHN l'lIANGE SF.CT lfMS CHANGE SECTl011 CHANGE SECTION , CHANGE C,

'R7 define't'e limst,

l. l . l.4 (TA prop Time E l . 2.'7 ' ' ' May Reepsire Change 3 l.l.1 Shutdown Margin for 2.l.8.8 h OR mont h Surveillance in SAM Tank MODES 1-4 may change Reactor Core DNHN Conventration

% 3.1 Feel enrithment limit 3.9.1 Refueling Baron 3.l.I.2 Shutdown Margin for 2.2.1 DNRR trop limit increases free 3.7 Concentration May Mnd)E 5 may change w/a to >3.25 w/o Change i

6.2.2.4 Nc.guire one SRO for 3.1.2.2 See IWNIE 5 Shutdown 3.2.4 Revise Figure and Change Care Alterations Margin Change Farmat, DNRR M.ter,en 3.1.2.4 See MODE 5 Shutdown 3.3.8 Table 3.3-1 ACTinN 6h Margin Change may be revised.

Neartor Prates tive lastiumentatson <

3.1.2.6 See MODE 5 Shutdown 3.I.3.6 Revise Insertion Margin Change Limit Fogure 3.1.2.A See MODE 5 Sheetdown Margin Change '

3.I.2.9 Table 3.5-1 may abange, Shutdown margin

' ~ ' ' ~ '

I I 7 T/I5/46) ( 9/0l/86) (12/22/85)

" ~~-

E (12/15/56)

I (12/15/86)

E

( 6 g2]86) (8) PH i TECH SPEC NATimE OF TECM SPEC NATINtE OF TECN SPEC NATINtE OF TECH SPEC NATLSE OF

. SECTION CilANCE SECTl010 CIIANGE SECTIOlt CllA11GE SECTION CHANGE d i.1.1. 3 - ifTC welE become more. 2.l.8.2 ' Redefine the PLilR 2.2.2 Ilenoval, requested. 3.3.1/3.3.2 RPS/ESFAS Surveillance 4

negative at Enc and 5tFR 10465, 3/26/86

. limit (01/01/87) Interval more positive at ROC CPC Addressable constant.

3.3.3.7- Add curve and change 3.3.3.I CEA Ifisalignment 3.6.3 Containment Isolation short-term and tran- ACTION statement (08/01/A6) Valves sient insertion limits need to be modified

  • 3.2.5 Clarification, RCS 3.2.1 RW/FT Lielt eey 3.8.1.8 A.C. Sources -

flow rate change (11/01/86) DG Testing Relief l 3.2.7 ASI ranges will 3.5.1 SIT beron concen- 6.2.2 Staffing shange tration and volume (08/01/86) requirements may a change a

3.3.3.6 Add RVIJss per License 3.5.4 IndSP boros concen- 3.4.8.2 P2R Spray Norrle Usage Conditions and CEOG tration and volume (08/05/86) Factor requiremente may change 3.10.1 Surveillance Reguire- 3.10.1 ACTIONS a,b may 3.4.R Pressure vessel ment 4.1n.1.2 may be have revised values (DA/nt/A6) Sueveellanic farseele relaxed, if desired of borea concentration i

3.10.2 Ad.1 3.3.3.7 for 3.3.3.8 Change Table 3.3.3.8 3.3.5 RPS, Allow Bypass part-length CEAs to list senke detector (09/01/A6) SG Eevel Msate Trip i in Control Roce 50 i NS20546

o CYCLE 2 RELOAD SCHEDULE (TECHNICAL SPECIFICATIONS)

  • (SHIP FUEL; 10/17/86)

GROUP A (90 DAYS)

(7/01/86) (10/01/86)

GROUP B (90 DAYS) (LOAD FUEL; 11/21/8C)

(8/21/86) (11/21/86) e GROUP C (90 DAYS) "

(MODE 5) i LEGE D (9/25/86) (12/25/86)

LEFT DATE: ilRC SUBMITTAL l RIGHT DATE: NRC APPROVAL f GROUP D (90 DAYS) l

'1 (10/01/86) 'g l3 li E'e-4 GROUP E (18 WKS.)  !

(7/15/86) (12/15/86) l$

l t l

i 3

v>

GROUP F (114 WKS. ) l (9/01/86) (12/15/86) ll

~

l __. - -. .. l . _ ---.__.-- l' l .-- -- . - -..l --.--.- --. _ ..3-.....- --- - - 1 l -- l 06/01/86 07/01/86 08/0'/86 1 09/01/86 10/01/86 11/01/86 12/0 t/86 01/01/87 02/01/87  ;

51

k e ,a g

JUN 101986 MEETING

SUMMARY

DISTRIBUTION

. Docket lNo(s): 50-382 -

NRC PDR Local PDR PBD-7 Reading JPartlow GWKnighton .

BGrimes ACRS (10)

EJordan Attorney, OELD Project Manager J. Wilson NRC PARTICIPANTS 2

J. Wilson G. Knighton C. Thcmas N. Lauben D. Fieno L Kopp J. Calvo I. Ahmed J. Luehman bcc: Applicant & Service List

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