ML19326D377

Responds to Util Re Implementation of 10 Reg Guides at Facilities.Forwards Comments & Info Requests Re Emergency Cooling Sys.Requests Response by 760206 to Allow Review Completion by 760312

ML19326D377
Person / Time
Site:	Midland
Issue date:	01/13/1976
From:	Schwencer A Office of Nuclear Reactor Regulation
To:	Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8006110386
Download: ML19326D377 (14)

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Local PDR SMacKay Docket W. 50-329 TIC EGoulbourne and c.,C LWR 2-3 File TR Branch Chiefs M 131976 RCDeYoung LWR 1 & 2 Branch Chiefs RHeineman JPansarella RWKlecker ACRS (16)

MWilliams JRBuc,hanan, ORNL Consumers Power Company TBAbernathy, DTIE ATTN:

Mr. S. H. Howell' LCrocker Vice President 212 West Hichigan Avenue Jackson, Michigan 49201 Gentlemen:

The enclosed comments and requests for information are in response to your letters of November 7, 1975, regarding the implementation of ten Regulatory Guides at your Midland Plant.

We haire also requested infor-mation concerning the emergency cooling system.

Your response to this request by February 6, 1976 will allow us to' complete our review by March 12, 1976. Please infom us within seven (7) days after receipt of this letter of your confirmation of this date or the date you will be able to meet.

Please contact us if you have any questions regarding the infomation requested.

. Sincerely, i

Original signed by.

A. Schwencer, Chief

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. Light Water Reactors Branch 2-3

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'1 Division of Reactor Licensing'

Enclosure:

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5 Request for Additional Information j

~ THIS DOCUMENT CONTAINS

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l Form AEC.)l3 (Rev. 9-53) AECM 0240

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JAN.131976 g

Consumers Power Company 2-i i

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- How.srd J. Vogel, Esq.

Knittle & Vogel 014 Flour Exchange Building 310 Fourth Avenue South i

Minneapolis, Minnesota 55415 Myron M.- Cherry, Esq.

Jenner & Block

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1 IBM Plaza Chicago, T114nois 60611

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Harold F. Reis, Esq.

l Lowenstein, Newman, Reis & Axelrad 1025 Connecticut Avenue, H. W.

l Washington, D. C.

20036 Honorable William H. Ward i

Assistant Attorney General

,. Topeka, Kansas 66601 Irving Like, Esq.

l Reilly, Like & Schneider

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200 West Main Street Babylon, New York 11702 l

James A. Kendall, Esq.

i 115 N. Saginaw Road

,e Midland, Michigan 49640 i

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ENCLOSU3E 000.0 GENERAL 000.1 Eased on our discussions of December 19, 1975, we understand that your design will conform with regulatory guides 1.1 (NPSH for ECCS pumps - 11/2/70), 1.7 (Control of Combustible Gas In Containment 3/10/71) and 1.49 (Power Letels).

't 000.2 Since the adoption of Appendix I to 10 CFR 50, Regulatory Guide 1.42 (As Low As Practicable Iodine Releases - 3/74) has been considered inoperative.

This guide will be replaced later this year and we will be glad to discuss the new guide with you after it has been issued.

000.3 Your letter of November 7, 1975 indicates that the degree of conformance to Regulatory Guide 1.70 remains undefined with regard to analyses for the Safety Analysis Report.

Please define the alternatives you wish to follow and provide the basis for such alternatives.

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JAN.131976 2-010.0 EFFLUENT TREATMENT SYSTEMS BRANCH 010.1 Regulatory Guide 1.52 provides guidelines for the design of ESF (6.5)_

air filtration systems.

Identify your ESF air filtration systems and provide the volumetric flow rate and adsorption bed depth for each system.

You indicate.that your design will not meet several positions of.Regulat6ry Guide 1.52.

Justify your design with regard to the following recommendations of Regulatory Guide 1.52:

C.2.a You should state that you will conform to the Guice.

C.2.c The fuel storage facility ventilation and filtration systems should be designated as seismic Category I.

C.2.j Filtration systems should be. totally enclosed and in-stalled in a manner which permits replacement of the train as a minimum number of segmented sections without removal of individual cc=ponents.

C.3.b You should state you will conform to the Guide.

C.3.j The design of the adsorber section should consider possible iodine desorption and adsorbent autoignition that may result from radioactivity induced heat in the adsorbent and coneccitant temperature rise.

Acceptable designs include a low flow air bleed system, cooling coils for the adsorber section, or other cooling. mechanisms.

The system design should provide for fire protection to inhibit adsorber fires. Combustible gas that may be generated by an adsorbent fire should be considered in the design.

C.4.d Replaceable components should be spaced five linear feet from mounting frame to mounting frame.

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JAN. I 31976 Auxihary and Power Conversion Systems Branch Request for Additional Midland Plant, Units 1 & 2 Docket Nos. 50-329/330 020.1 In order to per=it an evaluation of the ultimate heat sink and ther heat (9.2.5) removal systems, provide an analysis of the thirty-day period following a design basis accident listing the total heat rejected, the sensible heat rejected, the station auxiliary

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system heat rejected, and the decay heat release from the reactor.

In submitting the results of the analysis requested, include the following infor=ation in both tabular and-graphical presentations:

1.

The total integrated decay heat.

2.

The heat rejection rate and integrated heat rejected by the station auxiliary syste=s, including all operating pumps, ventilation equipment, diesels and other heat sources.

3.

The heat rejection rate and integrated heat rejected due to sensible heat re=oved from containment and the pri=ary system.

4.

The total integrated heat rejected due to the above.

5.

The maxi =um allowable inlet water te=perature taking into account the rate at which the heat energy cust be recoved, cooling water flow rate, and the capabilities of the respective heat exchangers.

l 6.

The available NPSH to the service water pumps at the minimum Ultimate Heat Sink water level vs. the required NPSH.

The above analysis, including pertinent backup infor=ation, should demonstrate the capability of the ulti= ate heat sink to provide adequate' water inventory and provide sufficient heat dissipation for the safe shutdown and cooldown of both units following a LOCA in one unit.

Use the methods set forth in the enclosed Branch Technical Position APCSB 9-2, " Residual Decay Energy for_ Light Water Reactors for Long Term Cooling," to establish the input due to fission product decay and heavy element decay.

Assume an initial service water te=perature based on the most adverse conditions for nor=al operation.

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JAN.131976

-3 213.0 REACTOR SYSTEMS 213.1 The monitoring of leakage from the Reactor Coolant Pressure Boundary (RCPB) is a safety function required by General Design Criteria 30.

The staff recommends the monitoring of airborne particulate radioactivity for implementation of GDC 30.

As stated in Regulatory Guide 1.45, at least one leakage detection system should remain functional to assist in evaluating conditions in containment following an SSE.

Describe' the monitoring systems or procedures for sampling and surveillance of the containment atmosphere that are able to detect a significant increase in RCPB leakage folicwing an SSE.and before the system can be brought to cold shutdown.

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310.0 ACCIDENT ANALYSIS 310.1 The source' term to be used by the applicant is not clear.

The source terms specified in Regulatory Guide 1.4 should be used for the Midland LOCA analysis.

310.2 An analysis of the iodine removal of the containment sprays should be provided, indicating the fraction of each form of iodine that will be removed from the containment atmosphere following a LOCA.

310.3 The applicant's proposal of meeting Guide 1.4, Paragraph C.2.3 is not in conformance with current NRC practice.

This should be revised to meet this Regulatory Guide.

The exposure doses from the LOCA should be based on a semi-infinite cloud for 8 + y.

310.4 It is noted that the applicant states, "If charcoal filters are employed in the (fuel) building ventilation system.

It is recommended that the spent fuel building be provided with an EST grade charcoal filter system which is automatically actuated by a high radiation signal.

310.5 Consumers Power Company asserts that the coatings to be used

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within the Midland containment building will meet the intended purposes of Regulatory Guide 1.54 adequately, although some documentation as to the qualification of the personnel applying

.the coatings will not exist due to agreements with labor unions made prior to the issuance of that guide.

To substantiate that assertien, the applicant should identify and estimate the quantity of all protective coatings applied within the containment.

Significant amounts of coatings which will enter the containment on equipment to be installed there should also be identified and estimated.

"Significant" is to be interpreted such that the total mass of unknown polymeric material within the con-tainment is likely to be no greater than 100 kilograms, and appears as small surfaces with a typical dimension less than about 10 cm.

Precoated small items may be identified by the resin base of their coatings, e.g., glyptal and phenolic heat-cured resin coatings. Thermosetting (" baked enamel") coatings having a phenol or phthalic acid base are likely to withstand

.LOCA conditions on small surfaces, even though non-rated.

A description of the "phosphating" surface treatment of 56 valves should also be supplied.

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JAN. I 31976

.s BRANCH TECHNICAL POSIT!ON APCSB 9-2 RESIOUAL DECAY ENERGY FOR LIGHT WATER REACTORS FOR LONG-TERM COOLING A.

8ACKGROUND The Auxiliary and Power Conversion Systems Granch has devaloped acceptJble assumpt1ons and fomolations that may be used to calculate the residual decay energy release rate for light water cooled reactors for long-tenn cooling of the reactcr facility.

Experimental data (Refs. I atd 2).on total beta and ga:mia energy releases for long half-life (> C0 seconds) fission products from thermal neutron fission of U-235 have been 3

7 considered reliable for decay times of 10 to 10 seconds. Over tnis decay tisce, even with the exclusion of short-lived fission products, the decay neat rate can be predicted to 6.ithin 10 percent of experimental data (Refs. 3, 7, and 8).

The short-lived fission products contribute apareciably to the decay energy for decay 3

times less than 10 seconds. Although consistent experiit. ental data are not as numerous (Refs. 4'and 5) and the results of various calculations dif fer, the effect of all uncer-3 tainties can be treated in the zero to 10 secorrd time range by a suitably conser<ative multiplying factor.

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BRAhCH TECHNICAL PC5!T!ON W

1.

Fission Product Oecay

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For finite reactor operating time (t ) the fraction of operating cower, ho (t, (3),

o o

• to be used for the fission product decay power at a time t, af ter shutdown suy be calculated as follows:

yhr=11A o p( a t,)

(1) n y, (, t,)

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(1 + K) h,(,t)~

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where:

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Fo fraction of operating power

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t, cumulative reactor operating time, seconds

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t, time aftfr shutdown, seconds

=

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K uncertainty factor; 0.2 for o i t, i 10 and 0.1 for 10 1tsi 10

=

A,, a, fit coefficients having the.'ollowing values:

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A, a,(sec 2)

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0.5980 1.772 x 10*

2 1.6500 5.774 x 10'I 3

3.*000 6.743 x 10-2 4

3.8700 6.214 x 10'3 5

2.3300 4.739 x 10'4 6

1.2900 4.810 x 10-5 7,

0.4620 5.344 x 10-6 8

0.3280 5.716 x 10~7 9

0.1700 1.036 x 10'I 10 0.0865 2.959 x 10-8 11 O.1140 7.585 x 10-10 The expressions for finite reactor operation may be used to calculate the decay erergy frora a complex coeratin nistory; howev6r, in accident analysis a suitacly conservative

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history saculd be used. For examale, end of first-cycle calculations should assee continuous operation at full power for a full cycle time period, and end of equilibrium cycle cal'culations should assume sopropriate fractiens of *he core *o have cuerated i

continuously for multiple cych times.

An operating history of 16,C00 hours is considered to be representative of 'an/ end-of-first, or equilibrium cycle conditions and is, therefore, acceptacle. In calculating the fission produce decay energy, a 20 percent ur. certainty f actor (K) snculd te added for any 3

ecoling time less than 10 seconds, and a factor of 10 percent should be added for cooling 3

7 times greater than 10 but less tnan 10 seconds.

2.

Hep y Elemant Dec 1 Heat The decay heat generation due to the heavy elements U-239 and N -239 may be calculated p%

according to the folicwing expressions (Ref. 6):

P ju-239) = 2.28 x 10~3 C

[1 - exp(-4.91 x 10'4 t )] [exp(-4.91 x 10' t,)]

(3) 25 o

Po (25 P(N 239) = 2.17 x 10.~3 25 - [0.007[1-exp(-4.'91x10'# t )]

C #

0 Po f25 4

-[exp(-3.41x10-6 t,) - exp(-4.95 x 10'4 t,)]

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+ [1 - exp(-3.41 x 10-6 t )] [exp(-3.41 x 10-6 g,))

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JAN. I 31976 P (U 23 f

=. fraction of operating power due to U-239 P (N'-239) p fraction of operating power due to N -239

=

p t,

caulative reactor operating time, secer.ds a

t, time af ter shutdown.. seconds

=

C conversion ratio, atoms of Pu-239 produced per atom of U-235 consumed

=

• 25 effective neutron sbsorption cross section of U 235

=

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= effective neutron fission cross :ection of U-235

• 25 The product of the terms C.

can be ccnservatively specified as 0.7.

• f25 The riuclear parameters for energy production by the neavy elements U-239 and ti -239 p

are relatively well known. Therefore, the nesvy element decay heat can de calcalated with a conservatively estimated product ter.n of C.

without applying any otner uncertainty correction factor.

20 3.

Figures 1, 2, and 3 give the residual decay heat release in terms of fractions of full reactor operating ;cwer baseo on a reasonately realistic reactur ope,ating tire of 16,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

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• After Shutdown, SEC Oi

r W JAN. I 31075 C. REFEREr.CES 1. J. F. Perkins and R. W. King, " Energy Release From the Qecay of Fission Prodvets, Nuclear Science and Engineering," Vol. 3, 726 (1958). 2. A. M. Perry, F. C. Malenschein, and D. R. Vandy, " Fission Product Af terheat: A Review of Experiments Pertirent to the Thermal-Neutron vission of 23tu," 00.NL-TM 4197, Oak Ridge National Laboratory, October 1973. 3. A..Tohtas, "'hc Energy Release Fron Fission Products," Journal of Nuclear Energy, Vol. 27, 725 (1973), a 4. J, Scobie, R. D. Scott, and H. W. uilson, "Seta Energy Release Following tne Thermal Neutron. Induced F'ission of 233U ar.0 235 U," Journal cf Nuclear Energy, Vol. 25,1 (1971), 5. L. Costa and R. de Tourrell, "Activite 5 et a Des Products d'une Fission de 23 0 et 23SPu," Journal of nuclear Energy, Vol. 25, 285 (1971,. 6. Pruposed ANS Standard, " Decay Energy Release Rates Following Shuto:.vn of uranium - Fueled Thermal Reactors," Americin Nuclear Society. Octeoer 1973. 7. J. Scobie 'and R. D. Scott, "Calcu14 tion of Beta Energy Release Rates Following Thernial Neutron Induced Fission of 3339, :P.g,.12Pu, and l' IPu," Jour nal of. Nuclear %ge=/ Energy, Vol. 25, 339 (1971). 8. K. Shure, " Fission Product Decay Energy," WAPD BT-24, Westinghouse Electric Corporatf or.. Decenbec 1961 b m ...ow. -.}}