ML20043A810
| ML20043A810 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/23/1990 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-90025, NUDOCS 9005230153 | |
| Download: ML20043A810 (5) | |
Text
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New Hampshire-
' Ted C. Feigenbaum i
Senior Vice P esident and
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' Chief Operating Officer j
4 NYN-90025
-January 23,.1990-1
~
United States Nuclear-Regulatory Conunission d
~ Washington, DC 20555.
- Attentions. Document Control Desk
References:
(a).. Facility Operating License NPF-67, Docket No. 50-443 (b) USNRC " Safety Evaluation Report Related to the Operation of Seabrook Station' Units 1 and 2,"_NUREG-0896, Supplement No.:8 May, 1989 (c) NHY Letter NYN-89140,; dated November 6,' 1989,L"NHY Power.
Ascension Test: Program,' FSAR Chapter 14= Revisions"
~
T. C. Feigenbaum to USNRC
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Subject:
NHY Power Ascension. Test. Program, FSAR Chapter 14 "evisions.
Gentlemen New Hampshire Yankee (NHY) has. committed to review any changescto thd initial test program as described in Chapter 14 of-the Final: Safety Analysis 7
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).
9 NHY proposed several FSAR Chapter 14 revisions. New Hampshire Yankee has;_
determined that three additionalistartup test' abstracts included'in-FSAR Chapter 14 require minor revisions as-discussed belows H
ST-28. Calibration'of' Steam and Feedwater Flow Instrumentation..
j The proposed change to this test revises the. method of: calibrating-
.l 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 wasito install-special', (temporary),
test instruments.at the feedwater flow primary elements, (venturis).
Instead;of using special test instruments,1 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
-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 1 instrumentation is acceptable. A pre-test and post-test calibration check will'also provide an added measure of assurance that the' accuracy of the permanent
(
s instrumentation remains within acceptable limits.
This change-in
.. methodology does not alter the scope of the test and will not create a 9005230153 900123 i
PDR ADOCK 05000443
'New bompshire Yankee Division of Public Service Company of New Hampshire O{
j P.O. Box 300
- Seabrooki NH 03874
- Telephone (603) 474 9521
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. United States Nuclear Regulatory Commission
' January 23, 1990 Attention: Document Control. Desk Page 2 1
situation where permanent plant instrumentation would-be-less reliable.
The methodology to make adjuotments'to other instrumentation, (e.g., steam flow), using-ST-28.during the initial power ascension will be unchanged'and-will use normal station procedures.
+ ST-30 Power Coefficient Measurement 1
The, acceptance criteria as stated'in FSAR Chapter 14. Table 14.2-5, Sheet 33 is inconsistent with the test objective.- The objective of the-power coefficient measurement test 11s to verify the design predictions lof-
-the powerLeoefficients given-in the Westinghouse Nuclear Design Report.
(NDR).. Showing that-the power coefficients are' conservative with respect to i
the values-contained in'the NDR,does nottprovide a verification of the-design predictions.
The measured values should be verified to be within q
some specified range of the acceptable values. The range should be based on
~
an estimate of the uncertainty of-the measurement ~ technique. The' expected uncertainty between the average-measured power coefficient l verification factor and the predicted power coefficient verification factor is 10.5'F/I.
Therefore 'this range should be selected as the test acceptance criteria.
i Incorporation of this change merely provides more: precise wording ~and more specific critoria for comparison of measured power coefficient values to-the j-predicted: design value.
ST-42 Water Chemistry Control 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 plant water chemistry control.
The correct-FSAR reference should be toL 9.3.2 and 9.3.4.
In addition Westinghouse: SIP 5-4;has been superceded by
- Westinghouse Guidelines for Secondary Water Chemistry."'
-i The above revisions to the' initial. test program have been evaluated pursuant to 10CFR50.59.
The evaluation determinedothat the initial test program revisions do not introduce an unreviewed safety question.
4 The enclosed FSAR ChapterE14 revised test abstracts for ST-28, ST-30 and ST-42 will be included in the next FSAR amendment.
Should you have any questions regarding this letter, please contact Mr. Terry L. Harpster', Director of Licensing Services at (603)~474-9521 extension 2765.
1 Very truly yours, Ted. C. Feigenbaum i
/
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lFCR 89-099'=Page' 4:
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.SB 1 E 2 Amendment 48 FSAR-January 1983 TABLE 14.2-5 (Sheet:31-of $3) s
- 28. -; CALIBRATION' OF STEAM: AND FEEDWATER FLOW' INSTRLMENTATION'
,0bjective.-
To calibrate the steam and ' feedwater ' flow instruments.
.)
- Plant Conditions / Prerequisites.
Portions of this test. will' be performed at. hott zero power conditions and at selected major power ~ plateaus (75%, 100%);as required by the startup-test sequence.
- - - -Test, Method
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Feedwater flow, as determined by special. test' instrumentation, will be com-
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. justments-of plant instrumentation will be made'to.obtain a best fit to.
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Tne steam and feedwater flow instrumentation has been calibrated.
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TABLE 14.2-5
-(Sheet 33 of $3) 30.
POWER COEFFICIENT MEASURDtENT O_b,j,ec t i ve To verify the design prediction of the power coefficient.
l 41 P_lant Conditions / Prerequisites This test will be performed at selected power plateaus ("*,,
$0%, 75%,100%)
as specified by the startup test sequence.
Test Method Generator load will be varied and data will be collected for delta-T, Tavg, and reactor power. Analysis of this data will be correlated to the power coefficient. This inferred actual power coefficient will be compared to the predicted power coefficient, Acceptance Criteria Qf.}
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FCR 89-099 Page 6
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sa 1 & 2 Amendment $6 FSAR November 198$
TABLE 14.2-5 (Sheet 45 of $3)
/
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- 42. WATER CHEMISTRY CONTROL Objective To demonstrate that chemical and radiochemical control and analysis systems function as described in the FSAR and verify that water chemistry eequirements can be maintained at various plant conditions.
'P'lant conditions / Prerequisites This test will be performed prior to criticality and at major power platears (HZP, 30%, 50%, 75%, 100%) as specified by the startup test sequence.
Test Method Samples of reactor coolant wil be analyzed to vetify 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
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[kI Control and alarm systems function as described in FSAR S::ne: 0.3,4, and l
water chemistry is maintained within limits established by Sestingh m *IP 5*
M and Technical Specification 3.4.8 and 3.7.1.4.
Analyzerresponsesagrek with analysis results.
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