ML20126E362
| ML20126E362 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/06/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8101230374 | |
| Download: ML20126E362 (4) | |
Text
1 AUG 6 1970 Docket r. M 3."5 2
e ConsuncIs Power Conpany K7f.. "r. Robert L. Unuctcr Electric Production Euperintendent - Nucicar
.'1" Ver t i'ichiran Avenue Jec'. sea. "ichfnan 4"201 Ce..:le::
In a tciraphone conversation of ?! arch 16, 1779, between ?!r. Dennin L. 'iernna of the '.)f vision of Reactor Licenoint ani!
- r. Gerald k'all:e of the Cone,wer, Pom.r Coupany, we advined you of a recent in-service dif ficultv vitS ri-furnacc-sensitiend stainicsc stoc1 cor.penent in a reactor prinary cooh, t nystcu and vc suggented that you promptiv invectf a, ate t!'c anelien'.11.it r of this inforantion to your facilf ty.
The difficulty involved full pancrntion crachint of a reactor vessc2 noz:1c snfo end. The crachod u tdrial was furnace-sensitized stainlecc stec1 which had experienced overctressing; no conclusive evidence with respect to the effect of corrodents has been established.
We are reviewing the potential applicability of this information to ottcr power reactors.
To assist us in performing this reviev, we request t'>nt you supp1v the follouing information (to the extent that f t is readilv available) reisting to the Big Rock Point Nuclear Power Plant within 3
dayc from receipt of this letter and inform un of the dates when the renainder of the information vill be availabic. To avoid repetition of materini that you may already have filed, you a:av reply to some questione b'y a brief sumary statement, includina specific reference to docunents alrealy on file.
1.
Identify all known sensitized stainicas steel within the reactor coolant preneure boundary,,connonantn of and including. portione of piping.
Include furnace-sensitized components affected by substantial field stress relieving, but not the heat affcete?
zones caused by field welds.
State location, type of material i
and sensitization procean.
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~~ jdefinitioh of reactor coolant pressure oundaryiseyclosn.d.
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1 AUG 6 1970 Consirvrs Pover Company 2_
2.
Specify the maximum stress icvels (calculnted or non ntred, i' kno'ra) those co sponents recef ve in service. Indicate whether t' e calculations or measurementn of stress icyc1 were baned on the "ac-built" condition, including effects of "as-installed" pf-in-hangers and restraints.
Sunnarize the results of any ffcid ncasurenents of piping displacement that have been perfor od.
including the systen conditions for v':f ch the censurenents were nade.
3.
Specify the normal external operating environnent of the conno matn listed above. Discuss the probability of external surf ace contact with corrodento.
Indicate the nornal water chenistry t'.at hna boca naintnined within the reactor coolant systen during both operating and' shut-dovn conditions, including the range of valuce for natcrials whose concentratione have varied apnreciably.
Include maarured t
valuco of oxygen and halide concentrationn.
4.
For each conponent licted, indicate whether the internal surface is normally in contact with flowing water, stagnant water, or staan, and indicate whether the configuration and operating con-ditions are such that a possibility exists of entrapnent of gneco vithin the sanoitized portion. Also, discuss whether posci'>1c corrodents could have conc into contact with the internal surfaces during cicaning or other preoperational exposure of these surfacen.
5.
Specify the nondestructive tests that have been perforned inter-nally and externally on each component listed since its instc11ation.
Indicate the acceptance critoria established for each tvpc of test, the sensitivity in terms of flau detcetion, and the resulte of these tests.
6.
Indicate whethor any destructive metallurgical examinatione have been performed on sensitized material rannved from the reactor coolant pressure boundary, or sannies thereof, and the results of such tests.
7.
Discuss the operating performance of leah detection systems during plant operation to date.
Indicate the current sensitivity of each systen.
8.
For each component listed, indicate the derree of accennikility which presently exf sts for the performnce of nondestructive tenta and inspectionn.
4
l AUG ~ 61970 Consumers Power Company 9.
Describe the plans you have developed for surveillance and non -
destructive tests of the sensitized stainless steel components of I
and within the reactor coolant pressure boundary, including a proposed timetabic.
In this connection, the recent exverience with furnace-sensitized stainless steci components indicates that unless a considerable amount of evidence attests to the current integrity of such components or unless valid technical reasons would preclude performing nondestructive tests, the perfornance of a program of nondestructive testing of a sizeable sample of j
such components may be appropriate at an early date. These i
I examinations should include dye penetrant testing and either ultrasonic testing or radiography.
l It is requested that forty copies of this information be subnitted to us.
}
i Sincercly, j
i Peter A. Morris, Director Division of Reactor Licensing DISTRIBUTION:
Enclosure:
ACRS (3)
Definition of Reactor Coolant H. L. Price Pressure Boundary C. K. Beck M. M. Mann cc: George F. Trowbridge, Esquire S. H. Hanauer Shaw, Pittman, Potts, Trowbridge & Madden P. A. Morris 910 - 17th Street, N. W-E. G. Case Washington, D. C.
20006 T. R. Wilson F. Schroeder D. J. Skovholt R. DeYoung R. Boyd W. Dooly, DR R. Engelken, CO (2) k File PDR HQ DR Reading 4 % u. 14. d.
Branch Reading R. H. Vollmer Licensing Assistant Technien1 Raviavar
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9-Definition of Reactor Coolant Pressure Boundary r
Reactor coolant pressure boundary / means all those pressure containing 1
components of boiling and pressurized water-cooled nuclear power reactors, such as pressure vessels, piping, pumps, and valves, which are:
(1) part of-the reactor coolant system or i
(2) connected to reactor coolant system, up to and including any and all of the following:
(a) the outermost containment isolation valve'in system piping which penetrates primary reactor containment, (b) the second of two valves normally closed during' normal reactor operation in system piping which does not penetrate' primary reactor containment, (c) the reactor coolant system safety and' relief valves.-
For nuclear power reactors of the direct cycle boiling water type, the reactor coolant system extends to and includes the outermost containment isolation valve in the~ main steam and feedwater piping.
L 1/ Components which are connected to the reactor coolant system and are part of the reactor coolant pressure boundary may be excluded from these requirements provided:
- i (a) For postulated failure of the component during normal reactor operation, the reactor can be shut down and cooled down in an orderly manner assuming makeup is provided by the reactor cool-ant makeup system only.
(b) The component is or can be isolated from the reactor' coolant sys-tem by two valves (both closed, both open, or one closed -and the other open). Each open valve must be capable of automatic actu-l' ation and its closure time must be such that for postulated failure of the component during normal reactor operation and assuming the
' t other valve is open, the reactor:can be shut down'and cooled down in an orderly manner assuming makeup is provided by the reactor coolant makeup system only.
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