ML20006F197

Forwards Revs to Chapter 14 of FSAR Re Power Ascension Test Program.Proposed Change to Test ST-28 Revises Method of Calibr Feedwater Flow Instruments & Obtaining Feedwater Flow Differential Pressure Data During Power Ascension

ML20006F197
Person / Time
Site:	Seabrook
Issue date:	02/15/1990
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90041, NUDOCS 9002270251
Download: ML20006F197 (6)

Text

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New kom shire 1

Ted C. l: y, Senior Vice President and Chief Operating C6cer l

1 NYN-90041

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February 15, 1990

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United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk f

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References:

(a) Fscility Operating License NPF-67. Docket No. 50-443 (b) USNRC ' Safety Evaluttion Report Related to the Operation

.of Seabrook Station Units 1 and 2 ' NUREG-0896. Supplement i

Nc. 8 May, 1989

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(c) NHY Letter NYN-89140, dated November 6, 1989, 'NHY Power Ascension Test Program FSAR Chapter 14 Revisions' l

Y. C. Feigenbaum to USNRC l

Subject:

NHY Power Ascension Test. Program, FSAR Chapter 14 Revisions j

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Gentlemen c

New Hampshire Yankee (NHY) has committed to review any changes.to the 1

initial test program as described in Chapter 14 of the Final Safety Analysis Report in accordance with the provisions of 10CFR50.59 and to report any such changes within one month of the changes [ Reference (b)).

In Reference (c).

NHY proposed several FSAR Chapter 14 revisions. New Hampshire Yankee has determined that three additional startup test abstracts included in FSAR Chapter 14 require minor revisions as discussed below:

l ST-28 Calibration of Steam and Feedwater Flow Instrumentation.

The proposed change to this test revises the method of calibrating feedwater flow instruments and obtaining feedwater flow differential pressure data during power ascension. The original method as described in FSAR Chapter 14 Table 14.2-5, Sheet 31 was to install special, (temporary).

test instruments at the feedwater flow primary elements (venturis).

Instead of using special test instruments, data will be obtained directly from the installed feedwater flow transmitters.

The calibration of the-installed feedwater flow transmitters is based on precision laboratory tests i

'of the flow venturis.

In addition, Yankee Atomic Electric Company Calculation.SBC-83, RCS Flow Rate Uncertainty Analysis, provides a justification that the accuracy of the installed instrumentation is i

acceptable. A pre-test and post-test calibration check will also provide an added measure of assurance that the accuracy of the permanent instrumentation remains within acceptable limits.

This change in methodology does not alter the scope of the test and will not create a 9002270251 900215 PDR ADOCK 05000443 P

PNV.

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New Hompshire Yonkee Ums.on of Pubhc bervice Company of New Hampshire

[MO P.O. Box 300

• Seabrook, NH 03874

• Telephone (603) 474 9521 gg

l United Statett Nuclear Regulatory Commission February 15, 1990 Attention: Document Control Desk Page 2 1

i situation where permanent plant instrumentation would be less reliable.

The 1

methodology to make adjustments to other instrumentation (e.g., steam fica), using ST-28 during the initial power ascension will be unchanged and l

will use normal station procedures.

• ST-30 Power Coefficient Measurement The acceptance criteria as stated in FSAR Chapter 14 Table 14.2-5, j

Sheet 33 is inconsistent with the test objective. The objective of the power coefficient measurement test is to verify the design predictions of the power coefficients given in the Westinghouse Nuclear Design Report,

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(NDR).

Showing that the power coefficients are conservative with respect to the values contained in the NDR does not provide a verification of the design predictions. The measured values should be verified to be within some specified range of the acceptable values. The range should be based on an estimate of the uncertainty of the measurement technique. The expected j

I uncertainty between the average-measured power coefficient verification factor and the predicted power coefficient verification factor is 10.5'F/2.

Therefore, this range should be selected as the test acceptance criteria.

Incorporation of this change merely provides more precise wording and more specific criteria for comparison of measured power coefficient values to the predicted design value.

ST-42 Water Chemistry Control

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This change merely corrects the references as stated in FSAR Chapter 14, Table 14.2-5, Sheet 45.

FSAR 9.3.4 is not a complete reference for j

plant water chemistry control. The correct FSAR reference should be to 9.3.2 and 9.3.4.

In addition Westinghouse SIP 5-4 has been superceded by i

' Westinghouse Guidelines for Secondary Water Chemistry.'

The abovo revisions to the initial test program have been evaluated i

pursuant to 10CFR50.59.

The evaluation determined that the initial test program revisions do not introduce an unreviewed safety question.

The enclosed FSAR Chapter 14 revised test abstracts for ST-28, ST-30 l

and ST-42 will be included in the next FSAR amendment.

l Should you have any questions regarding this letter, please contact i

(-

Mr. Terry L. Harpster, Director of Licensing Services at (603) 474-9521

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extension 2765.

Very truly yours, h(,fh 1

4 Ted. C. Feigenbaum

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United States Nuclear Regulatory Commission February 15, 1990

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Attention: Document Control Desk Page 3 cci Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia. PA 19406

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Mr. Victor Nerses. Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission j

Division of Reactor Projects j

Vashington, DC 20555 Mr. Noel Dudley NRC Senior Resident Inspector P.O. Box 1149 i

Seabrook. NH 03874 I

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CALIBRATION OF STEAM AND TEEDWATER FLOW INSTRUMENTATION i:

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Objective

'fo calibrate the steam and feedwater flow instruments.

Plant Conditions / Prerequisites I

1 Portions of this test will be performed at hot sero power conditions and at selected major power plateaus (75%,100t) as required by the startup test sequence.

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Feedwater flow, as determined by special test instrumentation, will be com-

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pared to steam and feedwater flow readings from plant instrumentation.

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Acceptance Criteria The steam and feedwater flow instrumentation has been calibrated.

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30. ~ POWER COEFFICIENT MEASUREMENT l

Objective To verify the design prediction of the power coef ficient.

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Ss 1 & 2 Amendment 56 FSAR November 1985 TABLE 14.2-5 (Sheet 45 of $3)

42. WATER CREMISTRY CONTROL Obiective i

To demonstrate that chemical and radiochemical control and analysis systems function as described in the FSAR and verify that water chemistry i

requirements can be maintained at various plant conditions.

P'lant Conditions / Prerequisites This test will be performed prior to criticality and at major power plateaus (HIP, 30%, 50%, 75%, 100%) as specified by the startup test sequence.

Test Method i

Samples of reactor coolant vil be analyzed to verify that primary chemistry requirements can be maintained. During power operation, samples of secondary plant water will also be obtained to verify that chemistry specifications are met.

These results will be compared with those from selected analyzers to demonstrate proper operation.

Acceptance Criteria iony 9,3,1 knk 9. 3.h

.N..*j Control and alarm systems function as described in FSAR S::h)en 9.314, and I

t water chemistry is maintained within limits established by Wesdagha"-- 'IP 5* 4 and Technical Specification 3.4.8 and 3.7.1.4.

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