ML20024G647
| ML20024G647 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/17/1973 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 9102140371 | |
| Download: ML20024G647 (6) | |
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NSE3 NORTHERN STATES POWER COMPANY M I N N E A P O L.l a. M I N N E S OT A 89401
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October 17, 1973 D
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')/4 l \\ \\g\\g n"*ym Mr. D J Skovholt W
QCl19 Assistant Director for gGM g 'b It p
Operating Reactors Yh M Office of Regulation U S Atomic Energy Cceraission to C
Washington, D C 20545
Dear Mr. Skovholt:
M0tlTICELLO NUCLEAR CENERATING PIANT Docket No. 50-263 License No. DPR-22 Response to September 5, 1973 Letter Concerning Inverted Control Rod Poison Tubes Your September 5, 1973 letter requested that we submit information concerning possible inverted control rod poison tubes.
Our response to each of the six areas questioned is as follows.
1.
Analyses of possible length and location of poison voids which could be caused by boron carbide redistribution.
Response
lhe Monticello control blades are similar in design and construc-tion to the Millstone blades discussed extensively in a July 23, 1973 report entitled, " Millstone Nuclear Power Station Unit 1, Reactor Control Blade Evaluation." Information regarding the g
mechanism and limitation of boron carbide redistribution is equally applicable to Monticello. Additional information is provided in the General Electric response, dated October 8, 1973, to ten AEC questions on the subject of inverted poison tubes. The Monticello complement of control blades in the reactor consists of 26 blades fabricated in Wilmington from January 25, 1969 to Itarch 26, 1969 and 95 blades fabricated in San Jose.
Mechanical accelerations from scram, mechanical vibration during operation and thermal cycling are functions which could contribute 9102140371 731017 PDR ADOCK 00,00263 P
eDn 7713
)
NO.
HERN CTATEO POWER C APANY to poison redistribution, if indeed one assumes Monticello rod blades are vulnerable to that phenomena.
The Monticello reactor has shown no evidence of boron carbide redistribution in these rods after 34 months of operation which includes 38 reactor scrams and 23 thermal cycles from cold shutdown to operating temperatures.
We have done extensive tests of shutdown margins on all rods, observing absolutely no indication of encroachment on safety cri-teria.
(See letter from Mr. L J Wachter to Mr. Boyce H Grier,
" Response to July 26, 1973 Letter on Shutdown Margin Testing,"
dated August 6, 1973.) Further, on several occasions we have conducted critical tests at cold shutdown conditions in ways to ascertain any significant conditions of reactivity asymmetry which may potentially develop between core quadrants or pic-shaped equal sections of the core and have observed no asymmetry indicative of significant poison redistribution.
These tests were particularly sensitive to the reactivity condition in the top of the core whers the boron carbide redistribution is postulated to occur.
(See letter from Mr. L 0 Mayer to Mr. J F O' Leary, " Supplemental Infor-mation to Cycle 2 Startup Report," dated August 9, 1973.) While the conditions have existed wherein redistribution might be predicted if inverted tubes exist, there has been no measurable effect on the core as would be anticipated from a significant amount of redistri-bution.
2.
The effect of such redistribution on normal operation, transients, and accidents.
Response
This question is answered by the Galeral Electric report referenced above.
3.
Proposed changes to Technical Specifications which will assure that all safety margins stated or implied in your FSAR are maintained.
Response
We concur with the General Electric report in that no changes to the Technical Specifications are required to preserve safety margins for the current cycle or af ter future reloads.
The response to this question in the General Electric report is based on the fact that we have performed shutdown margin tests on all control rods during the present cycle and is premised on the stated replacement criteria of defective control blades for meeting shutdown margin requirements for future cycles. As explained in our response to the following
NOR, (ERN CTATEO POWER CC DANY question, we may choose the option of performing shutdown margin tests in lieu of blade replacements during future outages.
In either of these alternatives, we see no need for Technical Speci-fication changes.
4.
Surveillance requirements to maintain adequate shutdown reactivity margins and monitor changes in poison distribution.
Response
in response to question 1 we outlined the testing done to date which showed no indication of boron carbide redistribution in the past.
We are following the status of the eddy-current testing techniques discussed in the General Electric report.
If at the time of our Spring, 1974 refueling outage the technique has been demon-strated to provide conclusive evidence of inverted poison tubes, we intend to cddy-current inspect each control blade in the reactor.
We will perform the following surveillance tests at the beginning of each reload cycle until we have conclusive evidence that no inverted poison tubes exist in excess of the.0025 delta k acceptance criteria discussed in the General Electric report:
a.
verify a shutdown margin of.0025 delta k on all rod.s having a calculated reload design shutdown margin less than.013 delta k at the most reactive ttne in the subsequent cycle.
b.
run cold critical quadrant symetry checks to verify symmetry as a check against any cluster settlement conditions.
5.
Your plans and schedules for change out of control rods.
Response
We have no plans to change out control blades at the present time.
We have a ibnf.ted number of spare control blades on site which are available for replacement. We believe that decisions on a replace-ment program should be based on:
a.
the findings of an ia-servke non-destructive test showing the number of inverted poison tubes relative to the.0025 delta k acceptance criteria, b.
evidence from the shutdown r.argin tests and symmetry tests that poison redistribution has indeed occurred, and c.
evidence f rom laboratory tests or from the inspection of exposed control blades that significant poison redistribution can occur.
I l
NOR 4ERN OTATED POWER CC PANY 4
1 6.
Expected curve of reactivity vs. burnup for the remainder of current operating cycle.
2 Respoase The attached curve shows the shutdown margin with the strongest control rod fully withdrawn for the entire Monticello cycle 2.
The present exposure in this cycle is approximately 2000 WD/T.
Yours very truly, 04 L 0 Mayer, PE Dir ctor of Nuclear Su port Services Lab /MHV/br cc: J G Keppler G Charnoff Minnesota Follution Control Agency Attn Ken Dzugan e
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AEC DI 71B11T10N FOR PANT 50 DOCKET MAm7 AL (TiliPORARY FORM)
CONTROL 1:0: 7713 FILE:
FR06:
!!EMO RPT OTHER Northern States Power Company Minneapolis, Minnesota 55401 l
L. O. Mayer, PE 10-17-73 10-19-73 X
TO:
Mr. Skovholt No Orig SENT LOCAL PDR X
CLASS UNCLASS PROP INFO IUPUT NO CYS REC'D DOCKET NO:
XX 49 l
50-263 DESCRIt' TION :
ENCLOSURES:
Ltr our 9-5-73 ltr....concerning inverted Control Rod Poison Tubes........
/,.~
- 7.,- y
-. s.. s.,; g;Q Do Not Removc PLANT NAME: Monticello FOR ACTION /INF0DiATION 10-23-73 AB BUTLER (L)
SClh'ENCER(L)
M IEMANN(L)
REGAN(E)
W/ Copies W/ Copies W/9 Copies W/ Copies CLARK (L)
STOLZ(L)
DICKER (F.)
W/ Copies W/ Copies W/ Copies W/ Copies COLLER(L)
VASSALLO(L)
KNIGHTON(E)
W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L)
SCHEltEL(L)
YOUNGBLOOD(E)
W/ Copies W/ Ccpics W/ Copics W/ Copics 7
INTERNAL DISTRIBUTION h REG FI W TECH REVI M DFliTON A/T IND
/IENDRIE GRIMES LIC ASST BRAI' MAN OCC, ROA P-506A / SCHROEDER CA G LL d IGGS (L)
SALTZMAN
/hUNIZING/ STAFF
/ MACCARY KASTNER GEARIN (L) y CASE v KNIGHT BALLARD GOULBOURNE (L)
PLANS GIAMBUSSO v PAWLICKI SPANGLER LEE (L)
MCDONALD BOYD
.,e SHA0 MAIGRET (L)
DUBE MOORE (L)(B'4R)
/ STELLO ENVIRO SERVICE (L)
DEYOUNG(L)(PWR) y HOUSTON HULLER SHEPPARD (F.)
INFO SKOVHOLT (L)
NOVAK DICKER SMITH (L)
C. MILES y
P. COLLINS ROSS KNIGHTON TEETS (L)
IPPOLITO YOUNGBLOOD WADE (E)
REG OPR_
y TEDESCO REGAN WILLIAMS (E)
/ FILE & REG 7CN(3)
VLONG PROJECT LDR WILSON (L)
MORRIS
/ LAINAS STEELE
.e BENAROYA HARLESS V01 THER 4
l EXTERt AL DISTRIBUTION l(4A
)
' 1 - LOCAL PDR Minnenoolis. Minn.
1 A'1 - DTIE(AEERNATHY)
(1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY
1 - ASLB(YCRE/SAYRE/
l-W. PENNINGTON, nn E-201 GT BR00KRAVEN NAT. LAB WOODl,PL/"H" ST.
1 -CONSULTANT' S 1-AGNED(WALTER KOISTE
[16 - CYS ACRS bOMkM&SENT TO LIC ASST.
NEWMARK/BLUME/AGBABIAN D! C-427-GT R. DIGGS ON 10-23-73 1-GERALD ULRIKSON...ORUL 1-RD.. MULLER..F-309 G
- - _ _ - _ - - - - _ _ _