ML20041D399

Responds to NRC Re Violations Noted in IE Insp Rept 50-309/81-29.Corrective Actions:Acceptance Criteria Will Be Utilized for Reactivity Computer Checkout.No Written Procedure Required for Shutdown Margin Demonstration

ML20041D399
Person / Time
Site:	Maine Yankee
Issue date:	01/04/1982
From:	Randazza J Maine Yankee
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20041D393	List: IR 05000309/1981029 ML20041D399
References
MN-82-01, MN-82-1, NUDOCS 8203050292
Download: ML20041D399 (3)

Text

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.t EDISON DRIVE MAMEe %s UAllHEE Aloml0P0lilER00MPARU*

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January 4, 1982 M

(207) 623-3521 v

MN-82-01 linited States Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 63] Park Avenue King of Prussia, Pennsylvania 19406 Attention:

Mr. Ronald C. Haynes, Director

References:

(a) License No. OPR-36 (Docket No. 50-309)

(b) USNRC Letter to MYAPCo dated December 4,1981 Inspection 50-309/81-29 (c) MYAPCo letter to USNRC dated April 28, 1981 - FMY-81-65 Proposed Change #84 (d) USNRC Letter to MYAPCo dated July 10, 1981 - Amendment 58 (e) Memorandum NED 80-335 dated April 16, 1980 " Verification of Shutdown Margin Technical Specifications (f) USNRC Letter to MYAPCo dated January 29, 1981 (g) USNRC Letter to MYAPCo dated November 6, 1978 Inspection 50-309/78-13

Subject:

Response to Inspection 50-309/81-29

Dear Sir:

In reply to the violation identified in the Notice of Violation, Appendix A of Reference (b), the following information is submitted:

Findim A: A written procedure for the shutdown margin demonstration was not established and implemented in the post refueling startup test program for Cycle 6 conducted in July and August, 1981.

Response: Maine Yankee does not conduct a test specifically to measure the shutdown maroin under the conditions which apply to the value in question (all rods in except the highest worth rod stuck out). Therefore, no written procedure is reouired.

The ARI-less-the-stuck-rod shutdown margin is calculated in the core design and analysis process. The calculation is verified by testing to assure that other measurable reactivity values have been accurately predicted by the methods used to calculate the ARI-less-the-stuck-rod shutdown margin.

The predicted measurable reactivity values are transmitted to the test team prior to startup testing. They are then utilized in conjunction with startup l

test results to determine whether preestablished startup test acceptance criteria have been satisfied.

Test procedures 11-2, Low Power Physics Test, and 11-3 Power Escalation Test include provisions for comparison of the difference between predicted and measured values with the acceptance criteria.

8203050292 820218 PDR ADOCK 05000309 C

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MAINE VANKEE ATOMIC POWER COMPANY US Nuclear Regulatory Commission January 4, 1982 Attn: Ronald C. Haynes, Director Page Two The measurement acceptance criteria for cycle 6 are discussed in the core performance analysis (Ref. c, pp. 125,126) which has been reviewed and approved by NRC (Ref. d).

The method by which the ARI-less-the-stuck-rod shutdown margin is verified is discussed further in Ref. e, f, g enclosed.

A review of these references will show clearly that Maine Yankee's method of assuring adequate shutdown margin has been specifically approved by NRC less than one year ago, in resolution of an essentially identical issue raised as an unresolved item in an I & E inspection in 1978.

During inspection 81-29, your inspector was made aware of I & E's previous investigation into this matter, yet he chose to raise it again.

We fall to see how an issue settled less than one year ago in our favor (Reference [g]) can now constitute a violation. Accordingly, we request withdrawal of this item nf noncompliance.

Finding B:. Procedure 11-2, Appendix A for the reactivity computer checkout did not have acceptance criteria to justify the validity of using the equipment for the startup physics measurements conducted in July and August, 1981.

l

Response

The reactivity computer checkout in Procedure 11-2, Appendix A is not a test referenced by Technical Specification 5.8.1 and thus it was not considered necessary to specify acceptance criteria in the procedure.

However, it is agreed that it would be good practice to have acceptance criteria specified for this check and acceptance criteria will be utilized in this procedure in the future.

Two checks were performed on the reactivity computer prior to its use for core 6 startup physics test measurements. The first test, (reactivity computer calibration) consisted of providing an input signal with an exponential generator and comparing the measured reactivity response of the reactivity computer to the value calculated from the time constant of the input signal.

The second test, (reactivity computer checkout) involved operating the reactor on a stable startup rate and comparing the measured response of the reactivity computer to the reactivity value calculated from the measured reactor startup rate.

The data from both of these checks was reviewed prior to the cycle 6 startup test program and the acceptability of the reactivity computer's performance was verified.

Appropriate written acceptance criteria have subsequently been developed for both checks. The core 6 test results were in conformance with these criteria.

MAINE YANKEE ATOMIC POWER COMPANY US Nuclear Regulatory Commission January 4, 1982 Attn:

Ronald C. Haynes, Director Page Three Based on the above, it is hereby requested that the severity level be diminished to a category of less severity because the situation, if left uncorrected, would not lead to matters of significant concern.

This conclusion is derived from the fact that the activities of concern were performed in an appropriate fashion although not documented adequately in procedure.

We trust this information is satisfactory.

Should you ha v any further questions, please feel free to contact us.

Sincerely yours, MAINE YANKEE ATOMIC POWER COMPANY O

c J. B. Randazz Vice-President JBR/bjp STATE OF MAINE

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)ss COUNTY OF KENNE8EC)

Then personally appeared before me, J. B. Randazza, who, being duly sworn, did state that he is a Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.

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Subject:

Inspection 50-50?/78-13 This refers to the inspection cond.cted by Mr. U. Lazarus of this office on October 10-13, and 16-18,1978, at the Maine Yankee Atomic Pc.ser..

Station, of cctivities authorized by i'RC License Io. DPR-36 and to the discussions of our findings held by Mr. Lazarus with fir. C. Frizzie of your staff at the conclusion of the inspection.

Arcas examined during.this inspectica are described in the Office of

-Q inspection and Enforcement. Inspectina Report which is enclosed with this -

letter. Within these areas, the inspection consisted of selective 1

eminations of prccedures and representative records, interviews with personnel, and observations by the inspector.

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Our inspector also verified the staps you have taken to correct the

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items of noncompliance brought to your attention in letters dated !!ove.Ther 9, 1977, August 17, 1976, and September 12, 1978. Ue have no further questions regarding your action at this time.

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Based on the results of this inspection, Mf uitbJ.0__rst#c3n_t,s,,

A a,ctiv,i_tj.es uas not corened in fy]j cng

. as set forth in Ine f.o:1ce at Violation, enclosed herewith as Apoenoix

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This item of noncorr.11ance has been categorized into the levels as doccribed in our corres W dence to you datsd Dece..:ber 31, 1974.

This notice is seat to yea u2:suant to the provisions of Section 2.201 cf the

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fGC's " Rules of Pet.ctice.' Pert. ?, Titic 10, Cecie of Federel R4,ulations.

days 0f you'r mf;.it. ci this not.ics. e written statc.r.5Ii,thjn * -" ' N Section 2.201 re ;ut res fl.e to suV.d t to this office, ui r

t or expianatian in repiy incluMng.

(1) correcti 3 stops which have been tnhen by you

-and the iv. u1M achiaved; (2) core..:ctive steos which uill be tak2n to'

. avoid #urther i'.ps of nenno.r.plicace; and (3) the date when full corpliance' V

ulll be achievad.

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In accordance with Section 2.790 of the !:TW" Rules of Practice," Part

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2, Title 10, Code of Federal P.eg.lhtions, a copy of this letter ced the enclosures will.bc placed in the ::RC's Public Docuacnt Room.

If this

. report contains any. infom.ticn that you (or your cor. tractor) bclieve to be proprietary, it is necessary that you make a written application l

~within 20 days to this office to tithhold such infcrmation frca public disclosure.

Any such application must be acccupanied by an affidavit executed by the onr,er of the infornation, which idcatifies the doce:ent

..n or part sought' to be withheld, and which contains a statement of reasons

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which addresses with specificity the items which will be considared by the Ccmmission as listed in subparagraph (b)(4) of Section 2.790.

The information sought to be withheld shall be incorporated as far as possible into a separate part of the afficavit.

If we do not hear from you in

' this regard.within the specified period, the report will be placed in i ~the Public Document Room.

Should you have any questions concerning this inspection, we will be a-pleased to discuss them with you.

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Sincerely, i

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L Eldon J. Brunner, Chief Reactor Operations and Nuclear-

-l Support Branch

Enclosures:

1, Appendix A, !!otice of Violaticn 2.

Office of Inspection and Enforcement Inspection Report liumber 50-309/78-13 cc w/cacls:~

E. Wood, Plant Superintendent E. U. Thurlow, President f

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Control Rod Drop Times Testing was performed in accordance with procedure 3-6.2.1.19, " Rod Drop Time Test and Functional Check,"

Revision 2.

(2)

Isotherml Temerature Coefficient Testing performed in accordance with procedures 11-2, Appendix C, "Zero Power Isothermal Temperature Ccefficient Measurement" and 11-3, Appendix H, "ITC Measurement at Powe r. "

(3)

Excore thrclear Instrumentation Calibration Performed in accordance with procedure 3-6.2.2.16. " Daily Calorimetric Adjustment," Revision 2.

(4) Shutdown f'arcin Deterninaticn The inspector identified the lack of a procedure to ccm-1 pute available shutdown margin by which the licensee could

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verify ccmpliance with technical specificaticns.

Using the CEA worths and various reactivity coefficients which had i

already been determined during startup testing, the licensee computed the hot zero power available shutdown margin which demonstrated compliance with Technical Specification 3.10.a.3.

The inspector reviewed the calculations and concurred with the licensee's determination of shutdown margin.

The licensee agreed to provide procedural coverage for computation of available shutdown margin during subsequent startup test-

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ing.

This item is unresolved pending review of the.xpleted j

procedure (309/78-13-02).

Except as noted in (4) above no other inadequacies were identified.

7.

Safety Iniection Svsten Procedures I

The inspector reviewed the following facility procedures to verify

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that adequate procedural guidance was available for operators for i

1 3 various situations under which a loss of coolant accident could occur.

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4Ct VERIFICATION OF SHUTD0'n':LMAllGIN TECidICAL SPEClfICATION

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REFERENCES:

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Haine Yankee letter to NRC. WMY 79-143, f.ecember 5, 1979.

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DISCUSSION:

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Technical Specification 3 10. A.3 requires that when the reactor is critical, the available shutd margin with sne CEA stuck out will not be less than 3 25 in reactivity.

Verification cf the required shutdown margin must be inferred by examining the results of Low Power Physics Testing, since the configuration of interest. All-Rods-In ( ARI) less one CEA stuck n.

9 ly.

cannot be measured. The major parameters that determine shutdown margin are

iN control rod worths, Moderator Temperature Coefficient (HTC) and Fuel N

Te=perature Coefficient (FTC). Each parameter is measured during the Low gy-Power Physics Testing and is demonstrated to meet the startup test criteria.

Q It should be noted that the test criteria is derived from the uncertainties p'.

placed on these paraseters in the safety analysis and is approved by the NRC g

yc prior to the issuance of the SER. With the three major parameters within the test criteria, it can be inferred that the shutdown margin is at least that "C

E assumed in the safety analysis as required by Technical Specifications.

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J. A. HANDSCHUH Reactor Physics Group C

Nuclear Engineering & Development Dept.

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-4.*t u ud E H. SOLAN Reactor Physics Group l

Nuclear Engineering & Development Dept.

M P. A. BERGERON,[

PWR Transient Analysis Group Nuclear Engineerin;; & Development Dept.

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pursuant to the provisions of Section 2.201 cf the NRC's " Rules of Practice 'This notice is sent to you l

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Enclosure:

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Appendix A, Notice of Violation n-m -- *y

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u 9A r,d. "w.r-Office of Inspection and Enforcement inspection Report murder MA i

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50-309/80-18

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E. Wood, Plaat Superintendent e:

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1. ,gf, st E. W. Thurlow, President 1 g:. yw d...[;4.,, M. N M Q

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.)E bl; 2 C.W ' R (closed) Varesolved Item (309/78-12 01). The Inspector determined that

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Q tj rs 3 N"*d U the licensee had found and correctec an intermittent nelfu9ction in his JiWW%.

1-digital eulti channel analyre which =ss causing the instrument to

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couble the nuncer of observed counts. Subsequent to this repair the y

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calibration check data returned to witnin acceptable limits and the I W.g;yg j

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licensee reswned ug sensitivity for Kr gng the 27 el getv=try because of its echanced (7 gllh,.M M k F K+ %'/0 3

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The inspector requested that the licensee analyze

/;g;4a.(*@s 4 a ccenen samle by both the Kontes flask and the 27 el geonetry. The m

results are listed below. Since the licensee's Kontes flask sample ya.

p agreed with the mobile lab results at the time of the split tasple, these results fetify returning to the 27 al geometry until another afig split s.aple is pe formed.

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Gas Decay Drum *3" XE.133 Kontes Flask 1.11 I-94 pp M

11/14/80

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XE-133 27 s1 1.14 E44 W[. @n g y' p

Y WMP-yQ 11/14/B0 18.71 E-f7 L.-b M MVQ) q.pyg ty Apg-f (Closed) Unresolved Item (3P/7913-02). The inspector determined that M. Nu br the licensee is cresently verifyirg the shutcown margin calculation I;%M*,W N.q gA F

@m rQyd (docurerted in applicatiens for core reload a.mercment) by cerfirming p' ?Nfj/j#_.- %

W A M,', b m the accuracy of the core perferr.ance model initially curing low powr h,Tf;p%,

~ Tf y.=;&rg J physics testing and swbsequently by periodic senttering of core per-q ym.@;i.

fermance parasuters. So loeg as r: reactivity aromaltes exist, the

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b p,Mh'lf".O gbpMM shutoown margin will continue to satisfy the technical specification i.

M p"MN [114 requi renent. Ba s ed en t'. t. m 'tica dxureted 'n licensee Pemeandt.e

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MD 80-335. 4HUBO. Me irm-*mr -~aered that a shutcown marjin h

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The inspector vertfled adequate shutcown nargin precicted for the M i w d '.. L l

QM present cors reload (V) and that the prediction redel has teen verified M*E. ;hN varr% -

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accurate. The inspecter had no further questices in this area.

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(Open) Follow-up Item (309/80-07-03). The irspector reviewed the

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n.w M %E licensee's iglementation of cornitments to satisfy the Interie Con-b'f* O # i N N i i"iN

.I"f 7.?/'a y.Q g tainment Purging Pesiticn described in A letter cated Octater 23, E '. ' i ngin *Qg+.,

1979, and WHY letter 79-146 dated Dacenter 12, 1979. The inspector 5;.; N d % p R verified that purge val.: have t*ree auto-initiated clostrq signels

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(C15. SIAS, radiation). E!ceking any of these signals will not inhibit

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the others from egersttrg to clcse tne valves. The ter pcrary cevices

?fM'.3%)]g T $l limiting the pur;e butterfly valves to 500 open have been re-oved M,'

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, tWr.Cdg il t'ecause no further pure,;1ng will te cerducted *his year cue to the 90 r.-

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Tre 11:ecsee expects to install a perinareet

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11miting device en the purge valves te+cre Jansarj 19E;, wever,

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"b MM@G should this ret te acccr pitshed the ? f censee has cors-tited te re.

4 7 install tem:arary limittag cevices nd/or prcvide acecuate acr.t.,15-m gcm trative controls to prevent crening the purge butterfly valves greater

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