ML20126B502

Forwards Procedure Comment Sheet on Mini Decay Heat Removal Sys Design Document,Sd TS-27,Revision 0.Document Is Incomplete Due to Omission of Info Re Instrumentation Alarm Setpoints.Requests Addl Info

ML20126B502
Person / Time
Site:	Crane
Issue date:	01/28/1980
From:	Jay Collins NRC - TMI-2 OPERATIONS/SUPPORT TASK FORCE
To:	Arnold R METROPOLITAN EDISON CO.
References
CON-NRC-TMI-80-015, CON-NRC-TMI-80-15 NUDOCS 8003130309
Download: ML20126B502 (9)

Text

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Ja nua ry 28, 1980

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NRC/ Tiil-30-015 Docket ho. 50-320 lir. R. C. Arnold Senior Vice President Metropolitan Edison Company 100 Interpace Parkway Parsippany, New Jersey 07054

SUBJECT:

Review of the HDMR System Description tnclosed are our comments to the NDMR System description document, SD TS-27,

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Revision 0.

Please note that based on the Burns and Roe cover letter from H. R. Lane to R. D. Elam, dateo i;ovember 16, 1979, the subject document is incomplete.

This is also reflected by no information given on such items as instrumentation alarm setpoints, identification of valves for flushing, and venting, and operating parameters for the isolation valves.

In order to expedite the review process, we have reviewed the first submittal.

The document was reviewed accoraing to the guidelines set in toe Criteria Document, Revision 6, and the B & R drawings M041, Revision 4, and liO43, Revision 3.

Since the NDHR System has been designed and is practically fully installed, we expect that more detailed information on the NDHR pump cubical fan / filter unit and the system leakage collection system would now be available. Hence, we request this information.

A l. ('gc%uD

,;J. T. Collins, Deputy Director NRC/TMI Technical Support Staff Enclosure as Stated cc:

See Distribution List 80031303<>q

R. C. Arnold 2

Metropolitan Edison Company Mr. R. F. Wilson George F. Trowbridge, Esquire Director, TMI-2 Shaw, Pittman, Potts & Trowbridge Metropolitan Edison Company 1800 M Street, N.W.

P. O. Box 480 Uashington, DC 20036 Middletown, PA 17057 Ms. Mary V. Southard, Chairperson Mr. J. J. Barton Citizens for a Safe Environment Manager, Si te Operations, TMI-2 P. O. Box 405 Metropolitan Edison Company Harrisburg, PA 17108 P. O. Box 480 Middletown, PA 17057 Dr. Wal ter H. Jordan 881 W. Outer Drive Mr. R. W. Heward Oak Ridge, TN 37830 Radiological Control Manager, TMI-2 Metropolitan Edison Company Dr. Linda W. Little P. O. Box 480 5000 Hermitage Drive Middletown, PA 17057 Raleigh, NC 27612 Mr. B. Elam Karin W. Carter, Esquire Manager, Plant Engineering 505 Executive House Metropolitan Edison Company P. O. Box 2357 P. O. Box 480 Harrisburg, PA 17120 Middletown, PA 17057 Honorable Mark Cohen Mr. L. W. Harding 512 E-3 Main Capital Building Supervisor of Licensing Harrisburg, PA 17120

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Metropolitan Edison Company P. O. Box 480 Ellyn Weiss, Esquire Middletown, PA 17057 Sheldon, Haroon, Roisman & Weiss 1725 I Street, N.W., Suite 506 Mr. E. G. Wallace Washington, DC 20006 Licensing Manager GPU Service Corporation Mr. Steven C. Sholly 100 Interpace Parkway 304 S. Market Street Parsippany, NJ 07054 Mechanicsburg, PA 17055 Mr. 1. R. Finfrock, Jr.

Mr. Thomas Gerusky Jersey Central Power & Light Company Bureau of Radiation Protection Madison Avenue at Punch Bowl Road P. O. Box 2063 Morristown, NJ 07950 Harrisburg, PA 17120 Mr. R. W. Conrad Mr. Marvin I. Lewis Pennsylvania Electric Company 6504 Bradford Terrace 1007 Droad Street Philadelphia, PA 19149 Johnstown, PA 15907 Ms. Jane Lee J. B. Lieberman, Esquire R. O. 3, Box 3521 Berlock, Israel, Lieberman Etters, PA 17319 26 Broadway New York, NY 10004

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Mr. R. C. Arnold 3

Metropolitan Edison Company Wal ter W. Cohen, Consumer Advocate Ms. Kathy McCaughin Department of Justice Three Mile Island Alert, Inc.

Strawberry Square,14th Floor 23 South 21st Street Harrisburg, PA 17137 Harrisburg, PA 17104 Robert L. Knupp, Esquire Ms. Marjoric M. Aamodt Assistant Solicitor R. D. #5 Knupp and Andrews Coatesville, PA 19320 P. O. Box P 407 H. Front Street Ms. Karen Sheldon Harrisburg, PA 17108 Sheldon, Harmon, Roisman & Weiss 1725 1 Street, N.W., Suite 506 John E. Minnich, Chairperson Washington, DC 20006 Dauphin Co. Board of Commissioners Dauphin County Courthouse Earl B. Hof fman Front and Market Streets Dauphin County Commissioner Harrisburg, PA 17101 Dauphin County Courthouse Front and Market Street Robert Q. Pollard Harrisburg, PA 17101 Chesapeak Energy Alliance 609 Montpelier Street Government Publications Section Bal timore, MD 21218 State of Library of Pennsylvania Box 1601 Education Building Chauncey Kepford Harrisburg, PA 17127 Judi th H. Johnsrud Environmental Coalition on Nuclear Power Dr. Edward O. Swartz 433 Orlando Avenue Board of Supervisors State College, PA 16801 Londonderry Township RFD #1 Geyers Church Road Ms. Frieda Berryhill, Chairperson Middeltown, PA 17057 Coalition for Nuclear Power Plant Postponement U. S. Environmental Protection Agency 2610 Grendon Drive Region 11I Office Wilmington, DE 19808 ATTN:

EIS COORDINATOR Curtis Building (Sixth Floor)

Holly S. Keck 6th and Walnut Streets Anti-Nuclear Group Representing York Philadelphia, PA 19106 245 W. Philadelphia Street York, PA 17404 Dauphin County Office Emergency Preparedness John Levin, Esquire Court House, Room 7 ansylvania Public Utilities Commission Front and Market Streets F. O. Box 3265 Harrisburg, PA 17101 Harrisburg, PA 17120 Department of Enviornmental Resources Jordon D. Cunningham, Esquire ATTN:

Director, Office of Fox, Farr and Cunningham Radiological Health 2320 N. Second Street P. O. Box 2063 Harrisburg, PA 17110 Harrisburg, PA 17105

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i Mr. R. C. Arnold 4

Netropolitan Edison Company Governor's Of fice of State Planning and Development ATTN:

Coordinator, Pennsylvania Cl ea ringhou se, P. O. Box 1323 Harrisburg, PA 17120 Mrs. Rhoda D. Carr 1402 Marene Drive Harrisburg, PA 17109 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, MD 20014 Ivan W. Smith, Esquire Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, DC 20555 Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, DC 20555 Atomic Safety and Licensing Appeal Panel U. S. Nuclear Regulatory Commission Washington, DC 20555 Docketing and Service Section U. S. Nuclear Regulatory Commission Washington, DC 20555 r

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PROCEDURE CCHMENT SHEET

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P rocedu re Numbe r/ Title SD TS-27 / MINI DECAY HEAT REMOVAL SYSTEM DESIGN DESCRIPTION REV O

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Ravicu Group 'NRR/NRC Telephone Ext. 392-72 9 Name/Date Al Ignatonis Jan. 21. 1980 Reject l Raasca

'Section-Comment Resolution Accept 2.1.1 (Cont. ) With regard to the MDHR pur.p design include a discussion

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of radiation shielding between the two pumps possibly augmented with a sketch.

2.1. 2 Thel $stsentencepertainingto i

I overpressure relief of the MDilR y

heat. exchanger appears to be j

incomplete. For~ example, mere I

inadvertent closure of the i

3 upstream isolation valv'e at the HX may not cause overpressure.

licwever, isolation of the valve,

downstream of HX and accompanied by an RCS overpressure transient will require' relief.

2.1.4 Fill in the blank spaces for t.

valves MDH-V1, - V2, - V18, and 0 ).

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-Vl9 (f.e., psig, and F

F,ill in blan)( spaces for valve

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TNS - V1007.

identify the remote flushing, 1 raining, and vent valves. Can use Dwg. M043, Rev. 3.

ou identify the relief setpoint

1. or the tube side pf the heat s -

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= 3.p..,3 PROCEDURE'CGlDfENT $HEET'"' ' ' -

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..s P rocedu te Numbe r/ Title 50 TS-27 / MItlI DECAY HEAT REMOVAL SYSTEM DESIGN DESCRIPTION. REV 0

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Rsvieu Group 'NRR/NRC Telephone Ext, aa nn Mana/Date Al Ignatonis Jan. 21. 1980

'Section-Corraent Resolution Accept Rej ect Reason 2.1.4 (Cont. ) exchangers at 235 psig. How-ever, according to Table 2,

' design pressure of tube side 5

is 150 psig. Resolve this discrepancy. -Secondly, provide basis 'for selecting a relief setpaint of 235 psig and dis-I charge. capacity of 53.5 gpm

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(Include the MDR pumps).

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2.2 Provide a tabulated electric load list for the MDHR5 com-ponents as coinnitted by Section 3.9A of the Design Criteria Doc., Rev. 6.

Provide the MDHR System HVAC kontrols description,.. -

3.1 fou state that the MDHR System 5

vill be filled and vented with 30 rated water matching the RCS

,-:oncentra tioh. -How will this ae doneJ The C;W system doesn't provide borated water' Nor does the preliminary operating pro-

cdure for MDHR identify such action.

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',. --., PROCEDURE COtafi.HT SHEET -'

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P rocedu tu flumbe r/ Title SD TS-27 / MINI DECAY HEAT REMOVAL SYSTEM DESIGN DESCRIPT10tl. REV. 0

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Review Group 'NRR/tipc Telephone Ext. A9 > 73g Na:2a/Date Al Ignatonis Jan. 21. 1983 Reject } Reason

'Section-Comment Resolution Accept l

3.1 (Cont.)

for the Tech. Nuc. Services Closed CoolinD Water Subsystem tie-in te the "A" Spent Fuel a

Cooler, you state that SF-C-1A is no longer operable.

According to Dag. M041, Rev. 4 and your description in para.

I 3.2 the.SF-C-1A cooler will be'

oper' ble. Furthermore, according l

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a to Dag. M041, Rev. 4. I question the.controlability of flow rate in TNS by throttling valve NS-V31A. Because part of the supply flow to TNS (via valve flS-V30A) will be diverted througt l

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the SF-C-1A cooler. The TUS.

return line tie-in shou'Id have

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i been located downstrews-of valve tlS-V31A. provide as'surance that you will have no problems in controlling flow thru the

[NS.

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3. 4 The spcial or, infrequent operation of items 3.4.1 thru 3.4.4 should be' provided prior to system use. Wify can't it be done how?

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' PROCEDtlRE'CCtMENT SHEET,

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P rocedu re Humbe r/ Title SD TS-27 / MINI DECAY HEAT REF.0 VAL SYSTEM DESIGN DESCRIPTION. REv 0 Revieu Group "NRR/NRC

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Telephone Ext. _ s _ n n Hana/Date Al Ignatonis Jan. 21.1980 1

Section.

Ccm:nent Resolution Accept Reject Reasca 3.5.4 For the postulated MD!lR HX tube failure,. the system will require shutdown so that it can be flushed to redace t

radiation levels.

I can see remote flushing on the primary l

side, but how will it be done 1,

on the secondary side (i.e.,

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itheTNSCCW)?

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l When the valve THS - VIOO7 i

i isolates on flow imbalance,

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leaking tobes in MDH - HX1A or MDH - HX1B may contaminate j

not only the INS but also the NSCCW system. Rnat assurance do we"have that this won't happen?

3.5.5 In the event of a gfos's system leakage, the MDHRS will be shut-down and isolated from RCS. What

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feill the al ternate system be used j

,for decay heat removal?

g 4.5 (ou state that '"a standby I

Component (i.e!, pump / heat exchanger) shodld not be isolated jo ensure the standby component i s 3 n a " ready s ta tus. " This

' s contradictory to the guide-ines of MDl!R operating, procedure

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-s-PROCEDURE CGHHENT SHEET

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P rocedu te Nu:r.he r/ Title SD TS-27 / MINI DECAY HEAT REMOVAL SYSTEM DESIGN DESCRIPTION. RFV. 0 Review Group 'flRR/rMC

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Telephone Ext. _ 392-72'.1 Hame/Date Al Ignatonis J6n. 21. 1930 t

Section-Cocaent Resolution Accept Rej ec t Reason 4.5 (Cont.)

which calls 'for normal operation 1

of one pump and one HX, and b

isolation of 'the other HX.

Please resolve it.

4 Table 1, Sheet 20 Include the mfgr. supplied t

i MDHR pu:pp performance curve. '

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Table 4 The alann setpoints should be provided prior to system use.

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Figure 1 The VEPC0 Seal Return Cooler Sheet 33 (MDH-HX1A & -liX1B) perfonnance aap is out of date. Note:

current decay heal is less ttjan 1.0 x 106 Btu /HR. Provide a 5

revision.

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