ML20033E086

Rev 0 to Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 8 Cycle 9

ML20033E086
Person / Time
Site:	Brunswick
Issue date:	01/31/1990
From:	Hill R, Lambert P, Moen S GENERAL ELECTRIC CO.
To:
Shared Package
ML19293A171	List: ML20033E085 ML20033E086
References
23A6456, 23A6456-R, 23A6456-R00, NUDOCS 9003080425
Download: ML20033E086 (25)

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23A64$6 Revision 0

~ Class 1 January 1990 23A6456, Rev.0 Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 8 Cycle 9 Prepared by:

A P. A. Lambert Fuel Licensin I

• /

Verified by:

N.7,'lil/ 7 7 Fuel Licensing I

S. C. M I

ar En ' ering

/

Approved by:

/

fey, h ager F elLicensi l0 A L D. Noble, Manager Reload Nuclear Engineering GENuclearEnemy 3

115 Curtner Avenue SonJose. CA 95125

)

Brunswick 2 z u uss Reland R Rev 0 i

j Important Notice Regarding Contents of This Report 3

Please Read Carefully This report was prepared by General Electric Company (GE) solely for Carolina Power and Light Company (CP&L) for CP&L's use with the U. S. Nuclear Regulatory Commission (USNRC)

)

to amend CP&L's operating license of the Brunswick Steam Electric Plant Unit 2. The informa.

tion contained in this report is believed by GE to be an accurate and true representation of the facts known, obtained or provided to GE at the time this report was prepared.

O The only undertakings of GE respecting information in this document are contained in the contract between CP&L and GE for nuclear fuel and related services for the nuclear system for Brunswick Steam Electric Plant Unit 2 and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract, or for any

'O purpose other than that for which it is intended,is not authorized; and with respect to any such unauthorized use, neither GE nor any of the contributors to this document makes any representation or warranty (expressed or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not O

infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.

O O

9-Page 2 O

t Brunswick 2 zuwa Reland B Rev 0 Acknowledgment The engineering and reload licensing analyses which form the technical basis of this Supple.

mental Reload Licensing Report were performed by S. C. Moen and H. H. Yeager of the Fuel En-I gineering Section.

D D~

9 9

9 9

9 hge 3 9

Brunswick 2 mua Reinnd S Rev 0 l

Plant unique itemas (1.0)*

)

Appendix A:

Analyses Values Appendix B:

Main Steamline Isolation Valve Out-of Senice Appendix C:

Use of New Safety Limit MCPR for Cycle 9

)

g Appendix D:

Decrease in Core Coolant Temperature Events Appendix E:

Feedwater Controller Failure Analysis Appendix F:

Maximum Extended Operating Domain

]

2.

Reload Fuel Bundles (1.0 and 2 0)

]

Fuel he Ovele inaded Number Irradiated BP8DRB299 6

60

)

]

BP8DRB299 7

148 l

BD317A 8

92 1

BD323A 8

92 9

New NBD330A 9

44 NBD329A 9

.124 Total 560 g

3.

Reference Core Imading Pattern (3.2.1)

Nominal previous cycle core average exposure at end of cycle:

22,323 mwd /MT C

Minimum previous cycle core average exposure at end of cycle from cold shutdown considerations-

" 323 mwd /MT Assumed reload cycle core average exposure at end of cycle:

23,049 mwd /MT Core loading pattern:

Figure 1 g

• ( ) refers to area of discussion in General Electric Standard Application for Reactor Fuel, NEDE-24011 P A 9, September 1988; a letter "S" preceding the number refers to the U.S. Sup-plement, NEDE 24011 P A 9 US, September 1988.

O Page 4 9

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Bru swick 2 nwu

="a Rev o 4.

Calculated Core Effective Multiplication and Control System Worth No Volds,20'C y

(3.2,4.1 and 3.2.4.2)

Beginning of Cycle, K Uncontrolled 1.099

)

Fully controlled 0.955 Strongest control rod out 0.976 R, Maximum increase in cold core reactivity with exposure into cycle, AK 0.013 3

5.

Standby Liquid Control System Shutdown Capability (3.2.4.3)

Boron Shutdown Margin (AK)

(DDm)

(20'C. Xenon Free)

C 600 0.038 6.

Reload Unique Anticipated Operational Occurrence (AOO) Analysis Input (3.2.3 and 4.3.1.2.3)

Values normally reported in this section are REDY inputs for cold water injection events only.

No transients were analyzed using REDY (See Appendix D).

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Brunswick 2 me amiand a nev o 7.

Reload Unique GETAB AOO Analysis Initial Condition Parameters (S.2.3)

Exposure:

BOC 9 to EOC9 2204 mwd /MT Fuel Penkinn Factors Bundle Power Bundle Flow Initial Design 1541 Radial Mial R. Factor (MWt)

(1.000 lb/hr)

MCPR

)

GE8x8NB 1.20 1.70 1.40 1.000 7.225 111.4 1.22 sJ GE8x8EB 1.20 1.60 1.40 1.051 6.808 118.3 1.21 BP8x8R 1.20 1.60 1.40 1.051 6.782 116.2 1.21 Exposure:

EOC9 2204 mwd /MT to EOC 9 Fuel Penkina Factors Bundle Power Bundle Flow Initial d_

Danign 1841 Radial Mial R. Factor (MWt)

(1.000 lb/hr)

MCPR GE8x8NB 1.20 1.64 1.40 1.000 6.952 113.0 1.27 GE8x8EB 1.20 1.55 140 1.051 6.561 119.7 1.26 BP8x8R 1.20 1.53 1.40 1.051 6.519 117.7 1.27

,3 8.

Selected Margin imprwement Options (S.5.1)

Recirculation pump trip:

No Rod withdrawallimiter:

No 7

'Ihermal power monitor:

Yes Improved scram time:

No Exposure dependent limits:

Yes Exposure points analyzed:

2 (EOC9 2204 mwd /MT and EOC9) 3 9.

Operating Flexibility Options (S.5.2)

Single. loop operation:

Yes*

Ioad line limit:

Yes 3

Extended load line limit:

Yes Increased core Dow:

Yes Flow point analyzed:

105 %

Feedwater temperature reduction:

No AR'I3 Program:

Yes Maximum extended operating domain:

Yes"

'Only for operation below the rated rod line.

O "See Appendix F.

Page 6 3

Brunswick 2 muu paa a nn o

10. Con wide AOO Analysts Results (S.2.2)

O Methods used: GEMINI and GEXI-PLUS

)

ACPR Flux O/A i

Event

(% NBR)(% NBR) GE8x8NB GE8x8EB BP8x811 Figure O

Exposure range: BOC9 to EOC9 2204 mwd /MT Load rejection without 447 120 0.16 0.15 0.15 2

bypass O

Exposure range: EOC9 2204 mwd /MT to EOC9 lead rejection without 403 124 0.22 0.21 0.21 3

l bypass For cold water injection events and feedwater controller failure analysis, see Appendices D O

and E.

11. local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary (S.2.2.1.5)

.O The r d withdrawal error event in the maximum extended operating domain was criginally analyzed in General Electric BWR Licensing Report, Marimum Extended Opemting Domain Analysis for Brunswick Steam Electric Plant, NEDC 31654P, dated February 1989. The l

MCPR limit for rod withdrawal error is bounded by the operating limit MCPRs presented in g

Section 12 for RBM setpoints shown in Tables 10 5(a) or 10-5(b) of NEDC-31654P.

O O

Page1 0

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Brunswick 2 nwu bland a neo

12. Cycle MCPR Values (4.3.1 and S.2.2)

)

Safetylimit: 1.06 Non pressurization events Exposure range: BOC9 to EOC9 GE8x8NB GE8x8EB BP8x8R Fuelloading error 1.19

)

Pressurization events Ontion A Ontion B

)

GE8x8NB GE8x8EB BP8x8R GE8x8NB GE8x8EB BP8x8R Exposure range: BOC 9 to EOC9 2204 mwd /hfr lead rejection without 1.32 1.31 1.31 1.25 1.24 1.24

)

bypass Exposure range: EOC9 2204 mwd /MT to EOC9 Load rejection without 1.33 1.32 1.32 1.29 1.28 1.28

)

bypass

13. Overpressurization Analysis Summary (S.3) 3 Pd Pv Event (psig)

{pJiig)

Plant Resnonse MSIV closure 1247 1281 Figure 4 (flux scram)

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Brunswick 2 muss mahda ano

14. Imading Error Results (S.2.2.3.7) 3 Variable water gap misoriented bundle ana!ysis: Yes Event M

Misoriented fuelbundle 0.13*

15. Control Rod Drop Analysis Results (S.2.2.3.1)

Brunswick Steam Electric Plant Unit 2 is a group notch plant operating in the banked position withdrawal sequence; therefore, the control rod drop accident analysis is not 9

required. NRC approvalis documented in NEDE 24011 P A 9 US, September 1988.

16. Stability Analysis Results (S.2.4)

O GE SIL 380 recommendations and GE interim corrective actions have been included in the Brunswick Steam Electric Plant Unit 2 operating procedures. Regions of restricted operation defined in Attachment 1 to NRC Bulletin No. 88 07 Supplement 1 are applicable to Brunswick 2 Reload 8.

O

17. Imss of coolant Accident Results (S.2.5.2)

LOCA method used: SAFER /GESTR LOCA g

Reference:

Brunswick Steam Electric Plant Units 1 and 2 SAFER /GESTR LOCA Loss of Coolant Accident Analysis, NEDC 31624P, September 1988.

The GE8x8EB LOCA analysis results presented in Sections 5 and 6 of NEDC 31624P g

conservatively bounds the LOCA analysis of the GE8x8NB fuel types. 'Ihis analysis yielded a licensing basis peak clad temperature of 1537'F, a peak local oxidation fraction of <0.31%

and a core wide metal water reaction of 0.036% The most limiting and the least limiting MAPLHGRs for the GE8x8NB fuel designs are as follows:

9 I

O

• ACPR penalty of 0.02 for the tilted misoriented bundle has been applied.

Page 9

Brueswick 2 muu a

an.o

17. Imss.cf. coolant Accident Results (S.2.5.2) (continued)

Bundle Type: NBD329A (GE8x8NB)

Average Planar MAPLHGR (kw/ft)

Exposure (GWd/MT)

Most Limiting i mt Limiting 0.0 10.70 11.43

~

1.1 11.65 2.2 11.16 11.86 4.4 11.46 5.5 11.63 12.79 8.8 11.0 12.56 13.01 13.8 12.44 12.96 16.5 12.18 12.70 11.67 27.6 38.6 10.05 49.6 8.02 9.00 54.2 5.90 56.2 5.93 Bundle 7ype: NBD330A(GE8x8NB)

Average Planar MAPLHOR (kw/fti Exposure

. (GWd/MT)

Most Limiting Least Limiting 0.0 10.60 11.38 1.1 10.77 2.2 11.74 6.6 11.56 12.58 8.8 9.9 12.07 12.73 11.0 12.24 12.87 13.8 12.32 12.94 16.5 12.16 27.6 11.67 38.6 10.04 10.35 49.6 7.92 8.96 54.0 5.91 5.94 3

56.1

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Page 10 J

nentcus oMMMMMo

=

eMMMMMMMMBL MMMMMMMMMMM

oMMMMMMMMMMMo i:: M M M M E N E M M M M M M l'c H M M M M M M M M M M M M P

':: M M M M M M M M M M M M M i;: H M M M M M M M M M M M M

':: M M M M M M M M M M M M M i:

"MMMMMMMMMMM" HMMMMMMMMMM l

"MMMMMMMMM" "MMMMM" l IIIIIIIII 1 3 5 7 9111315171921232527293133353739414345474951 5

8 FUEL TYPE A = BD323A D = BP8DRB299 (Cycle 7)

B = BD317A E = NBD330A C = BP8DRB299 (Cycle 6)

F = NBD329A 9

Figure 1 Core Imading Pattern l

Page 11

1 Brunswick 2 nwu maow a n~ o j

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Figure 2 Plant Response to Generator Imad Rejection Without Bypass (BOC9 to EOC9 2204 mwd /MT)

Page 12

)

l

r Brunswick 2 nwa

• • -'a Rev 0 m

INa-WW' dh I-N w

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=

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Figure 3 Plant Response to Generator Imad Rejection Without Bypass (EOC9 2204 mwd /MT to EOC9)

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a Brunswick 2 mua

->a a,s. o

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'O Figure 4 Plant Response to MSIV Closure, Flux Scram r se 14

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Brunswick 2 mr.m

-'s Rev.0 i

Appendix A D-1 Analyses Values The values used in the GETAB and AOO analyses are given in Table A 1. In addition, the

.j values reported in NEDE-24011 P.A 9 US, September 1988, are also provided.

j l

i I

Table A 1 j

i h

i Parameter Analysis Value NEDE 24011 Value Thermal power, MWt*

2436 2535 1 0.2 %

Dome pressure, psig*

1005 102012 psi

),

Rated steam flow, Mlb/hr*

10.48 10.9610.2%

Turbine pressure, psig*

949 196012 psi Core flow, Mib/hr*

80.9 "

7710.2%

- Reactor pressure, psia

• 1036 1035

)-

Inlet enthalpy, Btu /lb' 528 526.9 Non fuel power fraction *'

O.038 0.04 Number of S/RVs"*

9 11 Lowest setpoint, psig 1116 1105 + 1%

Y Recire pump power source On site""

Not Applicable D

y The indicated changes are consistent with the application of the pre approved methods outlined in Amendment 11 to NEDE 24011 P A and the Cycle 9 licensed operating conditions.

At increased (105%) core flow.

The indicated change is a result of the simulation of a valves out of service condition.

D'

"" Bounds operation with off site power source for reload licensing events for Cycle 9.

Page 15

O Bru:swick 2 muss Rdead S Rev 0 Appendix B o

Main Steamline Isolation Valve Out-of Service 1

i Reference B 1 provided a basis for operation of Brunswick Steam Electric Plant (BSEP) with l

6 one Main Steamline Isolation Valve Out of Service (MSIVOOS) (three steamline operation) and all S/RVs in service. For this mode of operation in BSEP Unit 2 throughout Cycle 9, the MCPR limits presented below are required, and the peak steam line and peak vessel pressures for the limiting overpressurization event (MSIV closure with flux r, cram) are 1224 psig and 1260 psig, O

'**P* 'i"*l -

Y MCPR Operating Limit O

BOC9 to EOC9 O

Ontion A Ontion B GE8x8NB GE8xSEB BP8x8R GE8x8NB GE8x8EB BP8x8R 134 132 132 130 1.28 1.28 O

Reference B 1 Main Steamline isolation Valve Out-of Service for Bmnswick Steam Electric Plant, EAS 117 0987, O

GE Nuclear Energy, April 1988.

O O

Page 16 i

Brunswick 2 nws6

=~ s amo Appendix C Use of New Safety Limit MCPR for Cycle 9 he analym required for this cyde were performed with a safety limit MCPR of 1.06 instead of the previous cyde's safety limit MCPR of 1.04. The implementation of this safety limit is a result of the utilization of the GE8x8NB fuel types as provided by Amendrnent 18 to OESTAR Il (NEDE 24011 P A). Any difference between this reload and the previous ones are due not only to cycle differences but also to the difference in the methods. Herefore, making direct comparisons between the two cycles may be inconclusive.

3

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Page 17 3

Brunswick 2 ms s6 maw a n<o l

Appendix D

)

Decrease in Core Coolant Temperature Events he loss of Feedwater Heater (LFWH) AOO and the HPCI inadvertent start up AOO are

).

the only cold water injection events checked on a cycle-by cycle basis. Dese analyses were run for the previous cycle and provided resultant values of less than 0.10 ACPR for the LFWH AOO and less than 0.16 ACPR for the inadvertent HPCI start up AOO. He limiting AOO for Cycles 8 and 9 is the load rejection without bypass with Option B ACPRs of 0.18 and 0.19, respectively. The cycle to cycle variations of the cold water injection events' ACPRs and of the load rejection event's ACPRs are smaller than the relatively large differences between the cold water injection events' and load rejection event's ACPRs. Furthermore, this trend is not affected by the loading of the GE8x8NB fuel design or the new core loading pattern. Derefore, these two AOOs will not be limiting for Cycle 9 and were not analyzed.

s h.

)

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Page 18

)

)

Bru2swick 2 mom

.. m i

Appendix E i

)

Feedwater Controller Failure Analysis 1

De Feedwater Controller Fauure analysis (FWCF) (maximum demand) AOO is an increase in coolant inventory event normally checked on a cycle by-cycle basis to determine if this AOO could potentially alter the cycle MCPR operating limit.

His analysis was run for the previous cycle and provided resultant Option B ACPR values of less than 0.08. He limiting AOO for Cycles 8 and 9 was load rejection without bypass with Option B ACPRs of 0.18 and 0.19, respectively. The cycle to-cycle variations of the feedwater contioller failure event's ACPRs and of the load rejection event's ACPRs are smaller than the relatively large differences between the feedwater controller failure event's and load rejection event's ACPRs.

i Furthermore, this trend is not affected by the GE8x8NB fuel design or the new core loading

)

pattern. Therefore, this AOO will not be limiting for Cycle 9 and was not analyzed.

)

A D

P b

D e

Page 19

i i

)

Brunswick 2

nwse,

=_i I Rev 0 i

j Appendix F 1

Maximum Extended Operating Domain i

)

Reference F 1 provided a basis for operation of the Brunswick Steam Electric Plant in the 1

Maximum Extended Operating Domain (MEOD). The reload licensing analysis performed for Cycle 9 and documented herein are consistent with and provide the cycle specific update to the reference F 1 analysis.

)

i Reference F 1 j

l Maximum Extended Opemting Domain Analysis for Brunswick Steam Electric Plant, NEDC 31654P,

)

GE Nuclear Energy (Proprietary), February 1989.

)

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Page 20 (Final)

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P ENCLOSURE 3 I

r CENERAL ELECTRIC COMPANY AFFIDAVIT LOSS OF COOLANT ACCIDENT ANALYSIS REPORT i-b 1

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1 GENERAL ELECTRIC C0MPANY AFFIDAVIT

1. J. S. Charnley, being duly sworn, depose and state as follows:

1.

I am Manager, Fuel Licensing, General Electric Company, and have been delegated the function of reviewing the information described in paragraph 2 which is sought to be withheld from public disclosure and have been authorized to apply for its withholding.

2.

The information sought to be withheld is contained in the General Electric Report entitled, " Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 - Reload 8, Cycle 9,"

NEDC-31624P, Supplement 2, Revision 0, Class III, dated December 1989.

3.

In designating material as proprietary, General Electric utilizes the definition of proprietary information and trade secrets set forth in the American Law Institute's Restatement of Torts, Section 757. This definition provides:

"A trade secret may consist of any formul a,

pattern, 3

device or compilation of information which is used in one's business and which gives him an opportunity to obtain an advantage over competitors who do not know or use it....

A substantial element of secrecy must exist, so that, except by the use of improper means, there would be difficulty in acquiring information....

Some factors to be considered in determining whether given information is one's trade secret are: (1) the extent to which the information is known outside of his business; (2) the extent to which it is known by employees and others involved in his business; (3) the extent of measures taken by him to guard the secrecy of the information; (4) the value of the information to him and to his competitors; (5) the amount of effort or money expended by him in developing the information; (6) the ease or difficulty with which the information could be properly acquired or duplicated by others "

4.

Some examples of categories of information which fit into the definition of proprietary information are:

Information that discloses a process, method or apparttus where

a..

prevention of its use by General Electric's competitors without license from General Electric constitutes a competitive econom-ic advantage over other companies; i

t i

i I

b.

Information consisting of supporting data and analyses, includ-l ing test data, relative to a process, method or apparatus, the application of which provide a competitive economic advantage, i

e.g., by optimization or improved marketability, c.

Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality or licensing of a similar product; 7

d.

Information which reveals cost or price information, production capacities, budget levels or commercial strategies of General Electric, its customers or suppliers; e.

Information which reveals aspects of past, present or future General Electric customer-funded development plans and programs of potential commercial value to General Electric; f.

Information which discloses patentable subject matter for which it may be desirable to obtain patent protection; i

g.

Information which General Electric must treat as proprietary

[

according to agreements with other parties.

5.

Initial approval of proprietary treatment of a document is typically made by the Subsection manager of the originating component, the y

person who is most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge.

Access to such documents within the Company is limited on a "need to know" basis and such documents are clearly identified as proprie-tary.

6.

The procedure for approval of external release of such a document typically requires review by the Subsection Manager, Project Manag-er, Principal Scientist or other equivalent authority, by the Subsection Manager of the cognizant Marketing function (or delegate) anel by the Legal Operation for technical content, competitive effect and determination of the accuracy of the proprietary designation in accordance with the standards enumerated above.

Disclosures outside General Electric are generally limited to regulatory bodies, custom-ers and potential customers and their agents, suppliers and licensees and then only with appropriate protection by applicable regulatory provisions or proprietary agreements.

7.

The document mentioned in paragraph 2 above has been evaluated in accordance with the above criteria and procedures and has been found to contain information which is proprietary and which is customarily held in confidence by General Electric.

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8.

The information to the best of my knowledge and belief has consis-tently been held in confidence by the General Electric Company, no l

public disclosure has been made, and it is not available in public sources.. All disclosures to third parties have beer, made pursuant to regulatory provisions of proprietary agreements which provide for maintenance of the information in confidence.

9.

Public disclosure of the information sought to be withheld is likely 1

to cause substantial harm to the competitive position of the General Electric Company and deprive or reduce the availability of profit

)

r making opportunities because it would provide other parties, includ-ing competitors, with valuable information.

6 l

t STATE OF CAllFORNIA

) ss:

00VNTY OF SANTA CLARA

)

f J. S. Charnley, being duly sworn, deposes and says:

That she has read the foregoing affidavit and the matters stated therein are true and correct to the best of her knowledge, information, and belief.

Executed at San Jose, California, this 3d day o _

mw, 197d.

J. A/ Charnley Ge(eral Electric Compa/

ny Subscribed and sworn before me this &

day of aw, 19 90.

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W1 NOTARY PUBLIC, STATE OF CALIFORNIA l

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MARY L KENDALL r

Nowy Publio Catilomia

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e SANTA Ct. ARA COUNTY s

My Comm. Exp. Mar. 26,1093 !

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