ML17278A841

Provides Supplemental Info to 860226 Application to Amend License NPF-21 Re Cycle 2 Reload.Use of Two Separate Sets for two-loop Operating Limits for Fuel Types & Separate Set for Single Loop proposed.Marked-up Tech Specs Encl

ML17278A841
Person / Time
Site:	Columbia
Issue date:	05/22/1986
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Adensam E Office of Nuclear Reactor Regulation
References
GO2-86-477, TAC-60804, NUDOCS 8605270188
Download: ML17278A841 (11)

Text

RECUL*

INFORNATIQN DISTRIBUTI STEl'i (RIBS)

ACCESSION NBR: 8605270188 DOC. DATE: 86/05/22 NOTARIZED:

NO DOCKET 0 FACIL:50-397 WPPSS Nuclear Progecti Unit 2.

Washington Public Poue 05000397 AUTH. MANE AUTHOR AFFILIATION SORENSENi C. C.

Washington Publi c Power Supply System RECIP. NANE RECIPIENT AFFILIATION

~ ADFNSAN> E. C.

BWR Pro Ject Directorate 3

SUBJECT:

Provides supplemental info to 860226 application to amend License NpF-21 re Cgcle 2 reload. Use of two separate sets for two-loop operating limits for fuel types 5 separate set for single loop proposed. Nark-up Tech Specs encl.

DISTRIBUTION CODE:

A001D COPIES RECEIVED: LTR ENCL SI ZE:

TITLE:

OR Submittal:

General Distribution NOTES'ECIPIENT ID CODE/NANE BWR *DTS BWR EICSB BWR PD3 PD 01 BWR PSB COPIES LTTR ENCL 1

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<5CO George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372.5000 May 22, 1986 G02-86-477 Docket No. 50-397 Director of Nuclear Reactor Regulation Attn:

E.

G.

Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing U.S. Nuclear Regulatory Commission

'Washington, D.C.

20555

Dear Ms,

Adensam:

Reference:

NUCLEAR PLANT NO.

2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS -

RELOAD LICENSE

'AMENDMENT (CYCLE 2),

SUPPLEMENTAL INFORMATION

Letter, G02-86-173, G.

C. Sorensen (SS) to E.

G.

Adensam (NRC), "Request for Amendment to Tecttnical Specifications - Reload License Amendment (Cycle 2)",

dated February 26, 1986 The reference letter requested certain changes to the MNP-2 Technical Specifications.

In submi tting changes to Section 3/4.2.1, Average Planar Linear Heat Generation

Rate, the Supply System incorrectly applied direction given by Exxon Nuclear Company (ENC) for establishing MAPLHGR limits while in single loop operation.

Exxon has evaluated the GE limits as being conservative with respect to the Exxon fuel design based on their DBA LOCA analyses and supports application of the adjusted GE MAPLHGR single loop limit.

To avoid confusion in interpreting LCO 3/4.2. 1, we

are proposing the usage of two separate sets of curves for each fuel type in both operating conditions.

The two sets will present the two loop

- operating limits for all fuel types and a separate set-for single loop operation.

For GE fuel, the new graphs for single loop operation do not represent a change to previous submittals.

For the Exxon fuel a conversion factor of.77 is being applied to mathematically apply slightly more conserva-tive nodal MAPLHGR limits than applied to GE fuel.

Direct application of the GE BCR233 fuel single loop APLHGR limit curve in monitoring MAPLHGR for ENC fuel is not possible with existing POMERPLEX software.

8b05270188 Bb0522 PDR ADOCK 050003'P7 P

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E.

G.

Adensam Page Two Ma/ 22, 19S6 RELOAD LICENSE AME t

T (CYCLE 2),

SUPPLEMENTAL IN R ATION To verify that use of the.77 multiplier applied to the ENC XN-1 fuel would be conservative for Cycle 2 operation when compared to the previously approved

.84 multiplier times the GE SCR233 type fuel MAPLHGR limits applied to the ENC XN-1 fuel, a comparative set of calculations was performed.

To account for differences in Bundle Average Exposure versus Average Planar

Exposure, a conservative axial peaking factor of 1.5 was divided into Average Planar Exposures to yield the comparative Bundle Average Exposure points.

Based on the results of these comparative calculations, the single loop MAPLHGR curve for ENC XN-1 fuel has been truncated at a bundle average exposure of 15,000 MWD/mt.

Although this supplementary information presents more conservative limits than those previously submitted

, the Supply System has reviewed this supplementary information.per 10 CFR 50.92 and determined that it does not:

I 1)

'Involve a significant increase in the probability or consequences of an accident previously evaluated because the analyses previously performed by GE for cycle one supported extended single loop operation and the Exxon evaluation of their OBA-LOCA analyses concluded application of the GE limits for Exxon fuel was conservative.

2)

Create the possibility of a new or different kind of accident from any. accident previously evaluated because the analyses is specifically designed to evaluate the most limiting accident.

3)

Involve a significant reduction in the margin of safety because the nature of the analyses and evaluation is to ensure conservative limiting conditions for operation are applied.

This change moves in a more conservative direction.

Additionally, this supplementary information has been reviewed with respect to 10 CFR 50.59 and does not represent an unreviewed safety question.

Attached are proposed technical specification pages reflecting this supplementary information.

Should you have any further questions, please contact Mr.

P.

L. Powell,, Manager, WNP-2 Licensing.

Very truly yours, S,.GQ c G.

C. Sorensen, Manager Regulatory Programs PLP/MRW/tmh Attachments cc:

JO Bradfute -

NRC C

Eschels - EFSEC JB Martin -

NRC RV E

Revell - BPA NS Reynolds - BLCP8R NRC Site Inspector LQtQ1 KK'Qe'98 661K ZZR 689 M083

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l.IST, OF FIGURES 2728'Llgi'3 COP FIGURE

3. 1. 5-1 PAGE SODIUM PENTABORATE SOLUTION SATURATION TEMPERATURE.. ~

~34 1-21 3.1. 5-2 30201 1

3. 2. 1-2

3. 2. 1"3

3. 2. 1-4 3.2. 1-5 3.2. 1-6 3.2. 3-1 SODIUM PENTABORATE TANK, VOLUME VERSUS CONCENTRATION RE(UIREMENTSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~

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MAXIMUMAVERAGE PLAHAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIALCORE FUEL TYPE SCR183........................

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR233........................

MAXIMUM AYERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPI.HGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIALCORE FUEL TYPE 8CR711...........,............

MAXIMUMAVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AYERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE SCR183 MAXIMUMAYERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AYERAGE PLANAR EXPOSURE, INITIAL CORE FUEl TYPE 8CR233 MAXIMUMAYERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS BUNDLE AYEPAGE EXPOSURE ENC XN-1 FUEL MINIMUM CRITICAL POWER RATIO (MCPR)

K~ FACTOR VERSUS CORE FLOW.....................................

3/4 1-22 3/4 2-2 3/4'-3'/4 2-4 3/4 2-4A 3/4 2-4B 3/4 2-4C 3/4 2-7 3.3.10-1 THERMAL'POWER LIMITS OF SPEC.

3.3.10-1.:.............

3/4 3-104 3.4. l. 1-1 3.4. 6. 1"1 THERMAL POWER LIMITS OF SPEC. 3.4.1.1"1.'"............

MINIMUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE (INITIALVALUES)......

3/4 4-3a 3/4 4-20 3.4.6.1-2.

4. 7-1 MIHIMUM REACTOR VESSEL METAL TEMPERATURE VFRSUS REACTOR VESSEL PRESSURE (OPERATIONAL VALUES).........

3/4 4"21 SAMPLE PLAN 2)

FOR SNUBBER FUNCTIONAL TEST...-......

3/4 7-15 3.9. 7-1 WEIGHT/HEIGHT LIMITATIONS FOR LOADS OVER THE SPEHT FUEL STORAGE POOl...............................

3/4 9-10 8 3/4 3-1 8 3/4.4. 6-1 REACTOR VESSEL WATER LEVEL...........................

8 3/4 3-8 FAST NEUTRON FLUENCE (E>lMeV) AT 1/4 T AS A

FUNCTION OF SERVICE LIFE.............................,

8 3/4 4-7 XX Amendment Na.

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GQ>W INDEX FIGURE

, 5.1-1

5. 1-2

5. 1-3 El(CLUSIOH AREA BOUNDARY.............................

LOM POPULATION ZOHE..................................

UNRESTRICTED AREAS AND SITE BOUNDARY fOR RADIOACTIVE GASEOUS AND LIQUID EFFLUEHTS.............

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5-2 5-3 5~4

6. 2. 1-1, 6.2. 2-la

. 6. 2. 2" 1b OFFSITE ORGANIZATION.............................. - -.

VHIT ORGANIZATION.................-...............-.

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3/4. 2 POWER OISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION

~e) avh4 Mbr~g bumhhC e.~pOSuve. 4v BHC.~gt 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not.exceed the limits shown in Figures

3. 2.1-1,

3. 2. 1-2, and 3. 2.1-3.

The limits oop opw090~ ~e s'rtoew 2w Fi'puces 'h.'2

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4 APPLICABILITY:

OPERATIOHAL CONDITION 1, when THERMAL POWER is greater than or equal to 25K of RATED THERMAL POWER.

G2lgl itablg.

Nth an AALHGR exoeeding theplimita of F!gore 3.2.1-1, 3.2.1-2, +3.2.1-3,3 2.>-'i@2.).

initiate corrective action wfthip 15 minutes and restore APLHGR to within Cv 3.2.1 the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 2',". oi RATED THERMAL POWER wi hin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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URt/EILLANCE REOUIREMENTS c dp 4.2.1 All APLHGRs shall be verified to be equal to or less than the limits determined from Figures 3. 2.1-1,

3. 2. 1-2,~ 3. 2.1-3> Z.2,l -4,'3.2 >-5 >tu 6 '3 '2 I-b a.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least }c~ of RATED THERMAL POWER, and c.

Initially and at least once per }2 hours when the reactor is operating with a LIMITIXG CONTROL ROD PATTERN for APLHGR.

WASHINGTON NUCLEAR - UNIT 2 3/4 2-}

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