ML17317A842

Forwards Response to Questions in from a Schwencer Re Addl Info on Containment Sump Test.Sump Mod Is Tentatively Scheduled for First & Fourth Refueling Outage for Unit 2 & Unit 1,respectively

ML17317A842
Person / Time
Site:	Cook
Issue date:	12/29/1978
From:	Maloney G INDIANA MICHIGAN POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:00110, AEP:NRC:110, NUDOCS 7901030066
Download: ML17317A842 (19)

Text

DOCKET 0y 05000315 050003 16 REGULAT<

INFORMATION DISTRIBUTION YSTEM (RI DS)

ACCESS I(

790.1 030066 DOC. DATE - 78/.I 2/'29 NOTARI ZED - W /fan FACI 0-315 ONALD C COOK N I, INDIANA 8 MICHIGAN ELECTRIC CO.

0-, 6 D()NALD C COOK P2, INDIANA 8, MICHIGAN ELECTRIC CO.

AUTH.NAME AUTHOR AFFILIATION MALONEY,G.P.

IN 8, MI PNR RECI P - NAMF.

BECI P IENT AFF ILIATION DENT()N,H. R.

OFFICE OF NUCLEAR REACTOR REGULATION

SUBJECT:

Forwards resoonse to questions in 781107 ltr frorq A Schwencer re addi info on containment sumptest.Sump mod is tentatively sched for first 8, fourth refueling outage for Unit 2 8 Unit I,respectively.

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INDIANA II MICHIGAN POWER COMPANY P. O. BOX IS BOWLING GREEN STATION NEW YORK, N. Y. 10004 December 29, 1978 AEP:NRC:00110 Donald C.

Cook Nuclear Plant Unit 1 and 2

Docket Nos.

50-315 and 50-316 License DPR Nos.

58 and 74 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission klashington, D.C.

20555

Dear Mr. Denton:

Enclosed please find our response to the questions contained in the =Attachment to Mr. A. Schwencer's letter dated November 7, 1978 regarding additional information on the containment sump test.

Modi-fications to the

sump, as recommended in the Alden Research Laboratory test report (submitted to the NRC via AEP:NRC:00112),

are tentatively scheduled to be completed during the first and the fourth refueling outage for Unit 2 and Unit 1 respectively.

Detailed schedule will be sent to you as it is finalized.

The attached information is being submitted at the request of the NRC staff and provides experimental and analytical verification of the adequacy of a previously reviewed and approved sump design.

In light of the

above, AEPSC interprets 10 CFR 170.22 as requiring that no fee accompany this submittal.

(

Reference:

10 CFR Part 170.22, footnote (2).)

GPM:em Sworn and subscribed to before me this 49 ~ day of December, 1978 in New York County, New York Not ry Public sUsAH GAY sTctNSR NOTARY PUBLIC, Stato of Now Yotk No.. Oj~anSY0 Quaffffod in iyow Yotk County Certificate fttod in How Yotk County Cotntnitudon Expftos March 30, 1980 cc:

(Attached)

Very'ruly yours,

/

, 6:

P. Maloneyt Vice President REGULATORY DOCKET FILE QOPy V90103COG~

Mr. Harold R, Denton December 29, 1978 AEP:NRC:00110 cc:

R.

C. Callen P.

M. Steketee G. Charnoff R. Malsh R.

W. Jurgensen D. V. Shaller-Bndgman

ATTACHMENT TO AEP:NRC:00110 RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION ON CONTAINMENT SUMP DESIGN AND TESTING

Sheet 1 of 10

RESPONSE

TO ITEMS 1, 5 AND 6 Alden Research Laboratory (ARL} has made several suggests,ons for design improvements of the containment sump.

Based on their model tests, AEP is planning to implement the ARL Recommendations.

Specifically, a)

Modification of the vent pipe design to insure that air will not be trapped in the sump.

b)

Removal of the horizontal perforated plate located below the sump suction.

c)

Installation of a vertical fine mesh screen behind the vertical grating at the sump inlet.

d)

Provide holes in the sump roof for additional venting.

e)

Extend the existing vent pipe beyond the maximum water elevation to avoid the water flow through the vent pipe.

All these modifications will be implemented in the plant during the first refueling outage of Unit 2 in the Fall of 1979 and the fourth refueling outage of Unit 1 in the Spring of 1980.

RESPONSE

TO ITEM 2'odel tests wi 11 be conducted to insure the sump design is not susceptible to air entrainment due to liquid effluent from the ice condenser drains and to the pipe breaks striking the water surface in the containment.

Once the tests are complete they will be submitted to the NRC.

RESPONSE

TO ITEM 3'odel tests will be conducted to demonstrate that pipe breaks in the vicinity of the sump will not create flow conditions which adversely affect the sump performance.

The results of the tests will be submitted to the HRC.

RESPONSE

TO ITEM 4:

Attached is an analysis based on preoperational data and model tests which demonstrate that adequate NPSH margin is available under runout conditions for the containment spray and residual heat removal pumps.

Sheet 2 of 10

RESPONSE

TO NRC QUESTION NO.

4.

&ST-ECT-Demonstrate that adequate NPSH margin is available under runout conditions for the Containment Spray (CTS) pumps and the Residual Heat Removal (RHR) pumps.

Entrance losses based on model tests and pipe friction losses based on preoperational tests will be utilized.

BASIS 1.

Active Containment Sump water temperature

- 190'F (Section 5.3.8, page 5.3-25, Unit 1 Appendix N of the D.c.

Cook Plant FSAR and Response to Question 212.29, Unit 2, Appendix Q of the D.C. Cook Plant FSAR).

2.

Containment Pressure

- 13.2 psia (Lowest allowable in D.C. Cook Technical Specifi-.

cations Section 3.6.1.4.

page 3/4 6-6).

3.

Active Containment Sump water level Elevation 602'-10" based on the water inventory from the RWST during the injection phase from "min" level to "lo" level.

When credit is taken for the water inventory to the "lo-lo" level in the RWST, the active containment sump level would rise to elevation 606'-2".

A further increase in level would occur if ice meltdown was included.

Preoperational Test Suction Pressure Data (2P0-050-537A).

5.

Sump Model Data (Alden Research Laboratory Report).

REFERENCES 1)

Crane Technical Pape~,No.

410, '"Flow of Fluids Through Valves, Fittings and Pipes".

2)

ASME Steam Tables, 1967 Edition.

3)

Hydraulics Institute Standards (pgs 57, 58, 88, 89, 90, 91).

4)

"Hydraulic Model Investigation of Vortexing and Swirl Within a Reactor Containment Recirculation Sump",Alden Research Laboratory.

I 5)

Appendix N and Q of the D.C. Cook Plant FSAR.

METHOD OF CALCULATION The Containment Spray pump flow was varied up to runout with the Residual Heat Removal pump constantly at its runout condition.

Data was taken at various points and is presented along with calculated values in the tables on pages seven and eight.

Curves were constructed based upon these tables and. graphically show the relationship between NPSHa and NPSHr' similar.method was used to generate data for the Residual Heat Removal pump.

Data is presented on pages nine and ten.

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