ML20106A218

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Affidavit of Dh Stevens Re Steam Erosion Hazards Analysis. Effects of Steam Erosion Cannot Prevent Safe Shutdown or Maint of Safe Shutdown
ML20106A218
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 02/01/1985
From: Stevens D
CLEVELAND ELECTRIC ILLUMINATING CO., GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
To:
Shared Package
ML20106A167 List:
References
OL, NUDOCS 8502110075
Download: ML20106A218 (38)
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UNITED STATES OF AMERICA C; ,_.,

NUCLEAR REGULATORY COMMISSION >

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Before the Atomic Safety and Licensing Board p, :55 In'the Matter of ) ,

)

THE CLEVELAND ELECTRIC ) Docket Nos. 50-440 ILLUMINATING COMPANY,'ET AL. ) 50-441

)

(Perry Nuclear Power Plant, )'

Units 1 and 2) )

' AFFIDAVIT OF DONALD H. STEVENS 8502110075 850205 PDR ADOCK O!M)00440

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UNITED STATES OF AMERICA NUCLEAR-REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

THE CLEVELAND ELECTRIC ) Docket Nos. 50-440 ILLUMINATING COMPANY, _E _T _A _L . ) 50-441

)

(Perry Nuclear Power Plant, )

Units-1 and 2) )

AFFIDAVIT OF DONALD H. STEVENS City of Washington )

ss:

District of Columbia )

Donald H. Stevens, being duly sworn, deposes and says as follows:

1. I, Donald H. Stevens, am a Senior Mechanical Engineer, Gilbert / Commonwealth, Inc. My business address is Route 10 and Pheasant Road,' Green Hills, Reading, Pennsylvania 19603.

I su-pervised the Steam Erosion Hazards Analysis performed by Gilbert Associates, Inc. (now Gilbert / Commonwealth, Inc.)

4 (" Gilbert") for the Perry Nuclear Power Plant ("PNPP").

Gilbert is the Architect-Engineer for PNPP. A statement of my professional qualifications and experience is attached hereto as Exhibit A.- I have personal' knowledge of the matters set forth herein and believe them to be true and correct.

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2. In my affidavit I describe the PNPP Steam Erosion Haz-ards Analysis.1/ The study was performed in response to Ohio Citizens for Responsible Energy's Issue No. 15, and was above and;beyond the analyses required to demonstrate compliance with regulatory design criteria.
3. The purpose of the Steam Erosion Hazards Analysis was to evaluate the design of PNPP in. order to determine effects of postulated piping failures, due to steam erosion, on the abili-ty of the plant to achieve and maintain safe shutdown. This was'an extensive study, which reviewed all safety-related sys-

, tems and components in plant areas containing steam and steam drsin piping. Over 4000 items were identified and reviewed.

, The conclusion of the Steam Erosion Hazards Analysis is that the design'of PNPP assures the ability of the plant to achieve and maintain.a safe shutdown condition in'the event of any credible-failure resulting from the effects of steam erosion.

4. The first task in the study was to identify all steam

.and steam drain piping, both safety-related and not-

~ safety-related. The second task was to-identify all plant areas containing suen piph.g.:l' This task was accomplished by a 1/ . Gilbert Associates. Inc., Report No. 2502, " Steam Erosion Hazards Analysis," Revision 1 (April 1984). This report was submitted to the NRC Staff by letter of May 15, 1984.

jb/ The Steam. Erosion Uazards Analysis reviewed PNPP Unit 1

-and common areas. Since Unit 2 is essentially a duplicate of Unit 1 for purposes of the study, the analysis provides assur-ance of the ability of Unit 2 to achieve and maintain safe shutdown.

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comprehensive review-of PNPP process and instrumentation dia-grams and physical drawings. A plant " area" was defined as a building or compartment separated from other areas by distance,

.or by physical barriers such as walls, sufficient to assure that the' postulated steam erosion hazards could affect only l systems and components in that area.

5. Third, all safety-related systems and components (both active and passive) in the plant areas containing steam and steam drain piping were identified.3/ Many areas of the plant contain'no safety-related systems or components, while other areas containing such systems and components do not contain steam or steam drain piping. Review of these areas was there-

-fore not required. All together, approximately 4,150 safety .

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class systems and components, including pumps, valves, cable, piping, tubing, instruments and other equipment, were identi-fled.

6. Fourth, in each area identified, failures in steam and steam drain piping were postulated which were assumed to pre-vent'the safety-related systems and components within the area from performing their safety functions. Each system and compo-nent then was reviewed according to the following preliminary steps:

3/ The PNPP Equipment Qualification Review List was used to identify ~ active safety-related components. Passive components were identified by comprehensive reviews of piping,' duct, tray and conduit drawings; circuit lists; and block diagrams.

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(1) If the safety function (s) of the system or com-ponent are performed by a redundant safety-related system or component located in an area separated from the postulated pipe

' failure being considered, no further review was required.

(2) If the safety function (s) of the system or com-ponent are not performed by a redundant safety-related system or component in a separate area, the item was reviewed to de-termine whether it is required to achieve or maintain safe shutdown, or is required to provide another important safety

-function,d/ for any postulated event. If not, no further re-view was required.

(3) If the system or component was determined to be required under step-(2), the item was further reviewed to de-termine whether it is required for the particular steam erosion failure or failures postulated as a hazard to that item, i.e.,

for the loss of the particular piping system or systems. If e

-not, no further review was required.

7. The fifth task consisted of more detailed analyses and reviews of-the approximately 270 items not resolved by the pre-

-liminary analyses described above. These analyses included more detailed reviews of system and component functional re-quirements, availability of other systems and components to 1/- "Other important safety functions" are functions not strictly required to achieve and maintain safe shutdown, but

- -which are otherwise required in emergency situations. Typical examples are containment isolation valves and instruments which

. provide important information to plant operators.

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perform the required function (s) under the particular condi-tions of the postulated pipe failure, and consequences of the loss of the particular function (s).

8. In a'few cases, resolution was supported by a determi-nation that the postulated pipe failure was not a credible event. These determinations were based on the expected life of the pipe in the-particular area of concern, calculated ac-cording to the Keller Equation. The Keller Equation is de-scribed in the Affidavit of Richard A. Pender. In addition, for each of these locations, the steam quality, temperature, velocity, and/or material properties were such that, based on industry experience, steam erosion failures would not be ex-pected to occur.
9. Attachment 1 illustrates the level of detail of the Steam Erosion Hazards Analysis.
10. Based on an exhaustive review of potential steam ero-sion hazards f'or all safety class systems and components, r:=

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I conclude that the effects of steam erosion cannot prevent safe shutdown or maintenance of safe shutdown of PNPP.

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Donald H. Stevens Subscribed and sworn to before me this lst day of February, 1985

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NOTARY PUBLIC My Commission Expires:

i ATTACHMENT 1 STEnM EROSION HAZARDS ANALYSIS Auxiliary Building RCIC Pump Room Area The attached portions of summary tables from the Steam

' Erosion Hazards Analysis Report illustrate the detailed review process outlined in the Affidavit. The reactor core isolation cooling:(RCIC) pump room area in the Auxiliary Building was chosen as a. typical example.

Table ~2 lists steam and steam drain piping systems possibly; subject to steam erosion. Review of the physical

~ drawings for each system identified plant areas containing any parts of:these piping sytems. This piping, including piping in the RCIC pump room area, is listed by area on Table 1.

The attached portions of Tables 3 through 6 summarize all safety-related items in the RCIC pump room area.

Table 3 lists safety-related piping and HVAC systems. The RCIC pump room contains five such systems which represent ap-proximately-15 individual piping and duct runs.

Table 4 lists safety-related instrument tubing. The exam-

, ple area contains 14 connections to 22 instruments.

Table 5. lists active safety-related components (e.g.,

pumps, valves, instruments). The example area contains 54 of

-these items.

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_ Table 6 lists safety-related electrical circuits, including pull boxes, terminal boxes and cable trays. The RCIC pump room area contains 70 circuits and one terminal box.

.The; example area contains approximately 150 items in Ta-bles 3.through 6. Of these, 18 items required more detailed review as described in 1 7 of the Affidavit. Tables 7 and 8 summarize the resolution of these reviews. The example area contains two items in Table 7 -(pipe, duct and tubing) and 16

-items in. Table 8 (circuits, active components, and equipment).

No items in the RCIC pump room area were identified which could prevent PNPP from achieving and maintaining safe shutdown in the event of a failure resulting from-the effects of steam erosion.

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  • Pags 1 of 2 3 . L*

TABLE 1 LIST OF STEAM PIPINC AEVIEWED BY AREA FOR STEAM EROSION Area Contains Reactor. Building Drywell B21 Main Steam, B21 Head Vent, E51 RCIC Steam Supply, E51 RCIC Head Spray Fitting, N22 Main Steam Drains Auxiliary Building Steam Tunnel B21-Nil Main Steam, B21-N22 Main Steam Vents and Drains, E32-MSIV Leakage Control, P61 Auxiliary Steam, P61 Drains, E51 RCIC and E12 Condensing Mode Steam Auxiliary Building RHR "A" E51 RCIC and E12 Condensing Mode (No effects.in Room "B" or "C") Steam, E51 Drain, E51 Turbine Exhaust Auxiliary Building RHR "B" E12 Condensing Mode Steam (No effect in Room "A" or ."C),

(N22 Drain is guard piped)

  • Auxiliary Building RCIC Pump Room E51 RCIC Steam, (P61 Aux. Steam)(1),

and Steam Drains Auxiliary Building RWCU Pump Room "A"' (P61 Auxiliary Steam)(1)

(No effects on ECCS and the P.WCU is not required for safe shur.down)

~ Condensate.Demineralizer Building N22 Main Steam Drain

. Turbine. Building & Heater Bay C85 Steam Bypass'and Drains, N11 Main and Reheat Steam N22 Drains, N25-N26 Heater Drains and Vents, N33 Steam Seal, N36 Extraction

-Steam, P61 Auxiliary Steam and Drains Auxiliary Boiler Building' P61 Auxiliary Steam

'Radwaste Building P61' Auxiliary Steam and Dra.ns

.(El. 602'-0" and 623'-0",- (Condensate return portions below RW-10 and RW-4,and approx. 623'-6" are not subject to steam 5'-0" S. of RW-C to 6'-0" N. erosion) of RWB, D-304-058 & 059)

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. c-  :,L TABLE 1 (Cont'd)

Area Contains Control Building M29 Control and Computer Room El. 679'-6" Humidification System (2)

NOTES:

-1. This P61-line is used for test only. It is normally isolated, and is therefore not subject to steam erosion.

-2. Consequences of breaks in the M29 system, including effects enveloping those of steam erosion breaks, were analyzed and found not to jeopardize safe shutdown (FSAR Section 3.6.1.2.2, p. 3.6-6, Am. 8).

There are P61 auxiliary steam condensate return lines in the radwaste, auxiliary, and turbine buildings. These lines are operated at less than 2000 F'and 275'psig, and are not: subject to steam erosion.

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7-Page 1 of 1 TABLE 2 SYSTEMS REVIEWED FOR STEAM EROSION System System and Piping Drawings 821 Main Steam 302-605 to 608; 304-026 to 028; CE 762E829, 762E276C 1C85 Steam Bypass 302-021; CE 767ES23 304-014, 015, 020, 251 E12 Residual Heat Removal 302-641 to 643;

' Condensing Steam Supply 304-640 to 650 E32 ~ MSIV Leakage control 302-341, 342; 304-341, 342

-M29- Control and Computer Room 913-018; Humidification System 923-115, 116; 304-725 N11 Main and Reheat Steam 302-011 to 014; 304-011 to 022

  • JN22. Main, Reheat, Extraction and 302-121 to 126; Miscellaneous Drains 304-501, 121 to 130 N25 High Pressure Heater. Drains 302-111, 112, 114, 115; and Vents 304-109 to 117

'N26 Low Pressure Heater Drains 302-113; and Vents 304-118 to 120 N33 Steam Seal 302-141; 304-141 to 144 N36 . Extraction Steam 302-041 304-041 to 045

  • P61 Auxiliary Steam 302-051 to 033 304-051 to 064 6

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Page 14 of 16 TABLE 3 (Cont'd)

AREA 5: RCIC PUMP ROOM REDUNDANT SYSTEM, ITEM SYSTEM: DWCS: DESCRIPTION OR RESOLUTION *

-E12 304-642 8" RHR Flush, 2 4" Heat Exchanger -

RCIC Suction.

E51 304-631 ESL Lines 1 304-632 Pump Suction, 4 Suppression Pool to E51-F031 M39 922-721 M39 Unit for 1 E51 - RCIC Pil 304-315 Suction and Return i Lines to Condensate Transfer i

P42 "A" 304-628 Emergency Closed 1 Cooling (Waters System "A"

  • l. Redundant system or component.

Not required for safe shutdown or other important safety functions. l 2.

3. Not required for this' event.

- '4. See Tables 7 and 8.

Revision 1 April 1984

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TABLE 4 (Cont'd)

~RESULTS OF REVIEW OF INSTRUMENT TUBINC Area 5: Aux. Bldg. - RCIC Pmp. Room 814/816 Process Instrument Inst. Impulse Redundant Sys./ Item Dug. Conn No. Panet Lines-Serve or Resolution

  • 703- A3 H22-P021 E51-N0558 (H) 3 E51-N055F (H) 706 Al H22-P017 E51-N055A (H) 3 Sh.;l E51-N055E (H)

A2 H22-P017 E51-N056A (H) 3 A3' H22-P017 E51-N056E (H) 3 A4 H22-P017 E51-N053 3

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E51-R002

< E51-N052

=

A5 H22-P017 E51-R003 3 E51-N007 (H)

A6 H22-P017 E51-R001 3 E51-N050 (H)

A7 H22-P017 E51-N051 (H) 3 E51-N003 (H)

AS H22-P017. E51-N051 (L) 3 E51-N003 (L)  ;

t F 4 B2 H22-P017 E31-N083A (H)

B3 H22-P017 E31-N083A (L) 4 B5 H22-P017 E51-R004 3

  • 1. Redundant system or component.
2. Not required for safe shutdown or other important safety functions. l Not required;for chis event.

3.

4. See Tables 7 and 8.-

Revision 1 April 1984

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TA3LE 4 (Cont'd)

._ , RESULTS OF REVIEW OF INSTRUMENT TUBING Area 5: Aux. Bldg. - RCIC Pmp. Room 814/816 Process Instrument Inst. Impulse Redundant Sys./ Item Dwg. Conn No. Panel Lines Serve or Resolution

  • A14 H22-P018 E12-N028 (H) 3 745 Low H51-P1346 C43-LT-N090A 1 press.

Conn.

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TABLE 5 RESULTS OF SAFETY RELATED COMPONENTS REVIEW BY AREA Key to column entitled " Redundant System, Item, or Resolution":

'l. Redundant system or component.

.2. Not required for safe shutdown or other important safety functions. l

3. Not required for this event.
4. See Tables 7 and 8.

k Revision'l April 1984

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' ' .Section 5

- 1 _Page l' TABLE 5 4

. TITLE' S-R EQPT ZONE AB-3 C. EQUIPMENT  ; DESCRIPTIONS .

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D NUMBER . SERVICE.

S ' EQUIPMENT Redundant System,' Item t or Resolution.

NIE31 N 0004A : LEAK' DETECTION. SYSTEM 4 RCIC EQUIP AREA AM3IENT TEt:PERATURE ELEMENT 4

MIE31 N 00048 LEAK DETECTION' SYSTEM RCIC EQUIP AREA ATIBIENT TEMPERATURE ELEMENT 4

NIE31 N 0005A . LEAK DETECTION SYSTEM EQUIP RCIC VEllT INLET TE!!PERATURE ELEMEllT 4

x1E31 N 0005B -LEAK DETECTION SYSTEll EQUIP RCIC VENT IHLET TEl:PERATURE ELEMENT MIE31 N 0006A ' LEAK' DETECTION SYSTEM EQUIP RCIC VEtiT GUTLET TE!!PERATURE ELEi1ENT 4

MIE31 N 00063 LEAK DETECTION SYSTEi1 ECUIP RCIC VENT DUTLET T Eil?LR ATUR2 LL E;10!IT

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Se'c tion 5

Page 2 TABLE 5.

-TITLE. : .S-R ECPT. ZONE'AB-3

.C EQUIPMENT , DESCRIPTIONS D HUMBER SERVICE S -EQUIPMENT . Redundant System item, or Resolution MIESI C 0001 REACTOR CORE ISOLATION COOLING 3 RCIC PUMP PUNP 3

MIESI C 0002 REACTOR CORE ISOLATION COOLIN3 PROCESS INSTRUMENT EQUIPMENT RCIC TURBINE

.NIE51 F 0510 REACTOR CORE ISOL ATI0H COOLIHG ~

RCIC TURB TRIP THROTTLE VALVE 2

ulE51 F 0510 REACTOR CORE ISOLATION COOLING 1 RCIC TURB TRIP THROTTLE VALVE OPERATOR-DC 2

plE51 F 0510 REACTOR CORE ISOLATION COOLING 2 RCIC TURB TRIP THROTTLE VALVE.

'SOLEHOID 2

41E51 F 0510 REACT 02 CO2E ISOLATIGH COOLING 3 RCIC TU2B TRIP THROTTLE VALVE LIMIT SlJITCHES

r- T;- -;7q Section 5

'Pahe 3'

, .TABl.E 5' TITLE : f S-R- EQPT ZONE A8'-3 C EQUIPMENT DESCRIPTIONS D NUMBER  : SERVICE .

Redundant . System, Item, or Resolution S- _ EQUIPMENT MIE51 N 0010 REACTOR CORE ISOLATIDH COOLING 3 STM SUPPLY LINE DRAIN POT LEVEL LEVEL SWITCH

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MIESI N 0037- . REACTOR CORE ISOLATION COOLING 3 STM EXHAUST LINE DRAIN POT LEVEL LEVEL SWITCH 3

MIE51 F 0011 REACTOR CORE ISOLATION COOLING CST TO RCIC PMP.

6 IHCH..CilECK VALVE NIE51 F 0030 REACTOR CORE ISOLATION COOLING SUPP POOL SUCT FOR RCIC PMP 6 INCH CHECK VALVE 3

~MIE51.F 0010 REACTOR CORE ISOLATION COOLING CST TO RCIC Pt1P~150 MOTOR OPERATOR klE51 F 0010 REACTOR. CORE ISOLATIDH COOL. SYSTEM 3 1 CST TO RCIC P!:P ISO 6 INCll GATE VALVES

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,. Page 4-i TABl.E 5' TITLE - S-R EQPT 2ONE AB-3L C EQUIPMENT ~ DESCRIPTIONS D NUNBER . SERVICE S- ' EQUIPMENT Redundant System, Item, or Resolution-MIESI F 0022 REACTOR CORE ISOLATION COOLING 3

RCIC TO CST 150 HOTOR OPERATOR 3

MIE51 F 0022 REACTOR CORE ISOLATION COOL. SYSTEM 1 .RCIC 10 CST 150 DC MOTOR'OPER 4 INCH GLOBE VALVES MIE51 F 0031 REACTOR CORE-ISOLATION COOLING SUPP POOL-SUCT ISO FOR RCIC-FM MOTOR OPERATOR REACTOR CORE ISOLATION COOL, SYSTEM 4 MIE51 F 0031 1 SUPP POOL SUCT. ISO FOR RCIC PM 6 INCil GATE VALVES MIE51 F 0045 REACTOR CORE ISOLATION COOLING 3 NS TO RCIC TURB.11AX P81145 PSI MOTOR OPERATOR 3

ale 51 F 0045 I:EACTOR CORE ISOL ATION COOL. SYSTEM 1 MS TO RCIC TUCB. M4X P81145 PSI 4 IliCli GLOSE VALVES

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"Section 5

~Page 5 TABLE 5

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TI71E_ ? S-R EQPT ZONE A8-3-'

C EQUIPMENT . DESCRIPTIONS.

D NUMBER ' SERVICE . .

5 EQUIPMENT . Redundant System, Item,'or Resolution MIE12 F 0036 RESIDUAL HEAT'RE'M VAL-SYSTEM 3 RHR TO RCIC PMP SUCT RELIEF 3 INCH X 4 INCH RELIEF VALVES 3

MIE51 F 0018 REACTOR' CORE ISOLATION COOLING RCIC TO LUSE DIL'CLR. REL.

1. INCH X 2 INCH-RELIEF VALVE EMERGENCY CLOSED COOLING SYSTEM 3 MIP42 F 0570 THECHAL EXP. RELIEF 3/4 INCH X 1 INCH RELIEF VALVE x1E51'F 0047 REACTOR CORE ISOLATION COOLING TURB D2N POT TO CRW 1 It:CH CHECK VALVE 3

MIE51 F 0061 REACTOR CORE ISOLATION COOLING t!TR LEG PHP DISCH.TO RCIC PMP 1-1/2. INCH CHECK VALVE

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Section 5--

- Page 6' TABLE 5 TITLE. : 5-R EQPT ZONE AB-3 C' EQUIPMENT DESCRIPTIO'HS D HUMBER SERVICE

~S EQUIPMENT Redundant System, Item,-(ar Resolution-REACTOR CORE ISOLATION COOLING. 3 ulE51 F 0062 WTR LEG FMP DISCH,TO RCIC PMP-1-1/2 INCH CHECK VALVE 1

d1E51 F 0090 . REACTOR CORE ISOLATION COOLING-THERMAL EXPANSION CHK.

Y I INCH. CHECK VALVE

  • 1H27 F 0783 FEEDt!ATER SYSTEM TEST LINE TO RitR 3 1 INCH CHECK VALVE klE51 F 0046 REACTOR CORE ISOLATI0H COOL. SYSTEM 3 RCIC PitP DISCH TO TURB LB OIL CLR.

MOTOR OPERATOR'

  • 1E51 F 0046 REACTOR CORE ISOLATION COOL. SYSTEM 3 1 RCIC PflP DISCll TO TURB LB OIL CLR.

2 IHCH GLOLE VALVES T

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Section 5-Page'7-:

TABLE'5) ae-

-TITLE : 5-R-EQPT ZONE AB-3

- C. EQUIPMENT: DESCRIPTIONS-D NUMBER SERVICE-S -EQUIPMENT ,

Redundant System, Item, or Resolution MIE51 F 0004 REACTOR COR'E' ISOLATION COOLING 3 '.

TURD DRN POT'TO CRW 150 CONTROL VALVE ON-OFF. SERVICE.

W1E51 F 0005 REACTOR CORE ISOLATION COOLING TURB DRM POT TO CKW 150 -

CONTROL VALVE

  • ON-OFF SERVICE 3
alESI F 8025 REACTOR CORE ISOLATI0H COOLING

'MS DRN POT TO COND ISO CONTROL VALVE OH-OFF SERVICE s

CONTROL VALVE ON-OFF SERVICE
  • 1E51 F 0054 REACTOR CORE ISOLATION'C00 LING 3

-MS DRM POT LEVEL. CONT.

CONTROL VALVE.

ON-OFF SERVICE m1E51 F-0;n4 REACTOR-CORE ISOLATION COOLING CONTROLS OPERATING AIR TO F004 SULENOID VALVE 1

Section 5-Page 8 TABLE 5 TITLEL

  • 5-R EQPT ZONE AB-3 C EQUIPMENT DESCRIPTIONS D HUMBER SERVICE: -

5 EQUIPMENT. _ Redundant System. Item, or' Resolution REACTOR CORE ISOLATION COOLING. 3 MIESI- F- 0405 CONTROLS OPERATING AIR TO F005 50LEH01D VALVE 3

MIE51 F 0425 REACTOR CORE ISOLATION COOLING CONTROLS OPERATING AIR TO F025 SOLEHOID VALVE 3

MIE51 F 3426 REACTOR CORE ISOLATIDH COOLING CONTROLS OPERATIllG AIR TO F026 SOLEt:0!D VALVE.

3 MIE51 F.0454 CEACTOR CORE ISOLATION COOLING C0t:TROLS OPERATING. AIR 10 F054 SOLEtiOID VALVE-

Mitt 39 B 0004 ECCS PUMP ROOM COOLING SYSTEn LCIC PUt:P K00tl AIR NAtDLIt:G UNIT FA;l

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.Section 5. -

.Page 9 TABLE 5 TITLE : S-R EQPT ZONE AB-3 C' EQUIPMENT' DESCRIPTIONS-D NUMBER _ SERVICE S EQUIPMCHT Redundant System,' Item, or Resolution WIM39 8 0004 -ECCSLPUMP. ROOM COOLING SYSTEM' ~3 1 RCIC PU;1P RM AIR-HANDLING UNIT MOTOR MOTOR d1E51 N 0404 REACTOR CORE ISOLATION COOLING 3 LIMIT SMITCH FOR VALVE F004 LIMIT SWITCil MIE31 N 0405 REACTOR CORE ISOLATION COOLING 3 LIMIT SWITCH FOR VALVE F005 LIMIT SMITCH MIE51 N C425 REACTOR CORE ISOLATION COOLING LIMIT SWITCH FOR VALVE F025 LI 11T SWITCH 3

MIE51 II 0426 REACTOR CORE ISOLATION COOLING LI!1IT SWITCil FOR- VALVE F026 LIllIT St3ITCil klE51 14 0454 REACTOR CORE ISOLATIDH COOLING 3 lit;IT SMITCil FOR VALVE F054

- LI:1IT S!JITCil

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NOTES TO TABLE 6 Notes to' explain numerical designations found in " Redundant System Item or Resolution" column:

1. Redundant system or component.
2. Not required for safe shutdown or other important safety functions.
3. Not required for this event.

4.- .See Tables 7 and 8.

- ' Some circuit designations end in a terminal box. A dash is shown in the l

,; resolution column for these items, to indicate that the circuit so f'

designated is reviewed by considering its parts. Terminal boxes are passive electrical boxes containing only wire and terminals. The circuits are physically continued with subsequent number designations,

~ and are reviewed in detail under the numbers designating the circuits finally. connected to the equipment served.

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Revision 1 April 1984-

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Page ILof 4 Section;5 TABLE 6 (Cont'd)

RCIC . PUMP RM. , AUX. BLDC. 574 '-04'.'

D-215-211

-LOCATION OF- REDUNDANT SYSTEM CIRCUIT SERVES ITEM SERVED DESICNATION -ITEM OR RESOLUTION IC61 CIA ~ IE51-C002 RCIC Rm. RCIC Turb. 2 1C95R119A lE51-F045 RCIC Rs. RCIC Valve 2 lE31T68A lE31-N005A- RCIC Pop. Rm. Leak Det. 4 IE31T69A lE31-N006A 'RCIC Pop. Mm. Leak Det.. '4 IE31T70A lE32-N004A RCIC Pop. Rm. Leak Det. 4 lE31T85B. IE31-N0028 RHR A Leak Det. 2 IE31T86B IE31-N0038 RHR A Leak Det. 2 1E31787B IE31-N001B RHR A Leak Det. 2 IE31T888 IE31-N0058' RCIC Pop. Re. Leak Det. 4 lE317898 IE31-N006B RCIC Pop. Rm.

. Leak Det. 4 1E31T90B IE31'-N004B RCIC Pop.'Rm. Leak Det. 4 IE31Til5XA lE31-N005A RCIC Pop. Re. Leak Det. 4 IE31Til6XA lE31-N006A RCIC. Pap. Rs. Leak De t . 4 IE31Tll7XA lE31-N004A RCIC Pmp. Rs. Leak Det. 4 IE51C28A lE51-F010 'RCIC Rm. RCIC Valve 2 IE51C40A. IE51-F045 RCIC Rs. RCIC Valve 2 IE51C48A IE51-F046 RCIC Rm. RCIC Valve 2 lE51C51A lE51-F022 RCIC Hm. RCIC Valve 2 IE51C59A IE51-C002 RCIC Km. RCIC Turb. 2 IE51C62A lE51-F031 RCIC Rm. RCIC Valve 2 IE51C65A lE51-F022 RCIC Hm. RCIC Valve 2

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. TABLE 6'(Cont'd). <

RCIC PUMP RM. . AUX. . BLDC. 5 74 '-04

D-215-211 (Cont'd)

~ LOCATION OF REDUNDANT SYSTEM CIRCUIT' SERVES ITEM SERVED DESICNATION ITEM OR RESOLUTION lE51C66A lE51-F059 RCIC Rs. RCIC Valve- -1 IE51C71A lES1-F059 RCIC Rm. RCIC Valve. . 1

.lE51C90A 'TB-1-431 RCIC Em., ' Terminal Box -

IE51C92A lE51-F045 RCIC Re. RCIC Valve 2 lE51C95A lE51-F031  ;RCIC Rs. RCIC Valve 2 lE51C96A- IE51-NO37 'RCIC Em. RCIC Drain' Pot. Lev. Sw. 2 IE51C97A 'lE51-N010 RCIC Rs.- RCIC Drain Pot. Lev. Sw. 2 lE51C98A 1E51-F045 RCIC Hm. RCIC Valve 2 IE51C100A lE51-F064 -RCIC Rm. RCIC Valve 2 IE51Cll2A TB-1-431 RCIC Re. Terminal Box -

IE51Cl36A lE51-C002 RCIC.Rm. RCIC Turb. 2 IE51Cl38A - IE51-C002 RCIC Rs. RcIC Turb. 2 IE51Cl39A T8-1-436 RCIC Re. Terminal Box .

IE51Cl40A TB-1-436 RCIC Re.- Terminal Box -

.1E51Cl41A lE51-F426 RCIC Rm. RCIC Valve 2 lE51C142A .lE51-N426 RCIC Rm. RCIC Inst. 2 lE51Cl43A lE51-N426 RCIC Rm. RCIC Inst. 2 IE51Cl44A lE51-F405- RCIC Rs. RCIC Valve 2 lE51Cl45A lE51-N405 'RCIC Rs. RCIC' Inst. 2 IE51Cl46A lE51-N405 RCIC Em. RCIC Inst. 2 IE51Cl47A lE51-F454 RCIC Rm. RCIC Valve 2

< v-

~

Page 3.of 4 Section-5 TABLE 6 (Cont'd)

RCIC PUMP RM., AUX. BLDC. 574'-04" -

D-215-211 (Cont'd)

LOCATION OF- REDUNDANT SYSTEM-

. CIRCulT SERVES ~ ITEM SERVED DESICHATION ITEM OR RESOLUTION'

~

IE51C148A' 21E51-N454 RCIC Re. RCIC Inst. 2 IE51C149A lE51-N454 RCIC Re. RCIC Inst. 2 lE51C1518 TB-1-437 RCIC Rm.. Terminal Box -

IE51C1528- .lE51-F425 RCIC Rm. .RCIC Valve 2 lE51C1538 IE51-N425 RCIC Re. RCIC Inst'. 2 lE51C1548 IE51-N425- 'RCIC Rm. RCIC Inst. 2-IE51C1558 -lE51-F404 RCIC Rm. RClc Valve 2 IE51C1568 lE51-N404 1RCIC Rm. RCIC Inst. 2 IE51C1578 -1E51-N404- RCIC Rm. RCIC Inst. 2 IE51C150A lE51-C002 RCIC Re.- RCIC Turb. 2 IE51D4A lE51-F010 RCIC Rs. RCIC Valve 2 lE51D6A lE51-F045 RCIC Rm.. RCIC Valve 2 IE51D7A lE51-F046 RCIC Rm. RCIC Valve 2 1E51D8A IE51-F022 RCIC Rm. -RCIC Valve 2 lE51D9A lE51-F510 RCIC Rs. RCIC Valve 2 IE51D10A lE51-F031' LRCIC Mm. RCIC Valve 2 lE51D13A lE51-F059 -RCIC Rm. RCIC Valve 2 IE51F3A lE51-C003 RCIC.Rm. RCIC' Pump 2 IE51R2A lE51-F510 -RCIC Rm. RCIC Valve 2

-IE51R5A. IE51-C002 RCIC Rm. RCIC Turb. 2 lE51R6A lE51-C002' RCIC Rm. RCIC Turb. 2

Page 4 of 4 Section 5 TABLE 6 (Cont'd)

-RCIC PUMP RM., AUX.LBLDC. 574'-04" D-215-211 (Cont'd)

LOCATION OF REDUNDANT. SYSTEM CIRCUIT SERVES ITEM SERVED DESICNATION ITEM OR RESOLUTION

-1E51R38A -lE51-F510 -RCIC Rm. RCIC Valve 2 IM39-B004 RCIC Hm. ECCS Cooling IM39FIA 2 1R61A966A lE51-N092 RCIC Rm. RCIC Inst. 2 1R61A967A lE51-N094 RCIC Rm. RCIC Inst. 2 1R61A977A lE51-C002 RCIC.Rm. RCIC Turb. 2 1R61A978A 1E51-C002 NCIC Rs. RCIC Turb. 2 1R61A979A lE51-N093 RCIC Rs. RCIC Inst. 2 1R61A980A lE51-N095 RCIC Rs. .RCIC Inst. 2

+ .,  ;-, , . -.

4 1

. . ' }3

- :p.

.4 Page 6~of 6"

TABLE
  • 7 :(Cont 'd) -

ITEM

  • MPL - CONCERN ' R ESOLUTIO'N2*

- 5. RCIC Room 3.5.1 E21- Pump Suction to E21-F031 - Flood Protection Design Containment Boundary 4.5.1  !!?2-P017 ' (11) and . (L) Lines for E31-N083A - Upstream E31-N0838 is redundant.

E31- Leak Detection.

6-10: Control, Condensate Demineralizer, Turbine, lleater Bay, Auxiliary Boiler, and Radwaste Buildings:

No mechanical, building service, or -inst rument lines within these areas require further resolution.

t 4

.. . ]-

<o-9' Page 14 of_.17' TABLE 8.(Cont'd)

ITEM SERIAL. (MPL #) CONCERN giuse8ER .(CIRCulT(S) f) 1.OCATION (FUNCTION) RESOLUTION **

5. RCIC Pump Room 5.5.1 IE!!-NOU4A HCIC Pump Houm Leak Detection RCIC llow leak detection 6.5.3 !EllTIGA RCIC Pump Ruum .s va i l a tel e . Sullicient 6.5.9 IEllTillXA RCIC Pump Hoon seg.arat ion between temperatare elements and circuits to detect small breaks.

5.5.2 I E !!-N004 ti RCIC Pump Huom f.eak Detection HCIC llow leak detection 6.5.6 IEllT90tl MCIC Pump Huom available. Sullicient separatiun between t emperat ure element s and circuit s to detect small breaks.

+- -;=-/ - - -

~

37

.s.

n #

d  % .

1Page 15'ofLl7-

- TABLE 8'(Cont'd)-

' ITEM

-SERIAL' (MPL $)' CONCERN NUMBER' (CIRCUIT (S) #) LOCATION (FUNCTION)' RESOLUTION 2*

5.5.3 IE31-N005A' 'RCIC Pump Room Leak-Detection .RCIC flow leak detection

~

A

. 6.5.1- ' lE31T68A' RCIC. Pump Room. available. Sufficient 6.5.7- IE31Til5XA. RCIC. Pump Room ,_ separation between t emperature element s and circuits to detect small breaks.

5.5.4 lE31-N0058 .RCIC Pump Room Leak Detection 'RCIC flow leak detection 6.5.4 IE31T888 -RCIC Pump Room available. Sufficient separation b' etween -

. temperature elements and circuits to detect small breaks.

5.5.5 - !E31-N006A RCIC Pump Room Leak. Detection RCIC flow leak detection 6.5.2 lE31769A' 'RCIC Pump Room available. Sufficient 6.5.8 IE31Til6XA RCIC Pump Room separation between temperature elements and circuits to detect small breaks.

5.5.6 - IE31-N006B RCIC Pump Room Leak Detection RCic flow leak detection 6.5.5 IE31789B- RCIC Pump Room available. Sufficient separation between temperature elements and circuits to detect small breaks.

. 5.5.7 lE51-F031 ECIC Pump Room CIV Flood Protection Design

.f EXHIBIT A DONALD H. STEVENS

, Mechanical Engineer (Nuclear)

Extensive experience in engineering design, specification and analysis for the nuclear power generation industry.

EXPERIENCE: GILBERT / COMMONWEALTH since 1979

1984 to. Project Mechanical Engineer - Currently performing Present Continuing Services for General Public Utilities u Nuclear-Corporation's Three Mile Island Nuclear Station, Unit 1.

'1982-84 Task Manager, Nuclear Power Systems - Deep Basing Support Systems and Facilities Inte-

. _ gration Program in support of the U.S. Air Force, Ballistic Missile Office. Directed

! the technical and planning efforts associ-ated with the analysis of alternative nu-

. clear power generating technologies. These

. efforts included: conceptual design of an integrated nuclear power system; perfor-mance analysis; and life-cycle cost estimating and assessment of technical and schedule risk. Additional responsibilities included technical interfacing with all

'~'

other engineering groups of'the deep base system.

'l?83 Supervised Steam Erosion Hazards Analysis for Cleveland Electric Illuminating Compa-ny's-Perry Nuclear Power Station.

^

-1982 Project Mechanical Engineer, Continuing ic Services, for Metropolitan Edison Company's Three' Mile Island Unit'1, including piping systems modifications and resolution of equipment and system design questions..

L1980-84 Supervision of dynamic incidents analysis, design and design review'for Perry Nuclear-

'PowerLStation, Units'1 and 2, including pipe ~ rupture, jet impingement, pipe whip, missiles, flooding, local environmental hazards, and structurally and

. hydraulically-transmitted loads due to dy-namic incidents. Work included: evaluation of plant design against regulatory L

.:a_.

" Donald H.'Stevens

Page 2 criteria; development of licensing docu-ments and responses to NRC and intervenor questions; and management of

. interdisciplinary efforts to implement pro-tective measures.

1980 Systems for post-accident sampling and analysis of reactor coolant, reactor con-tainment sump, and reactor containment at-mosphere, to NUREG 0578 criteria, for Three Mile-Island Unit 1; Perry Nuclear Power Plant, Units 1 and 2; South Carolina Elec-tric & Gas Company's V. C. Summer; and Rochester Gas & Electric Company's R. E.

Ginna Stations.

1979-80 Radwaste evaporation / solidification facili-ty for Three Mile Island Unit 2 cleanup and

~

recovery operation, including: chemistry and radiology of feedstreams and feedstream

-pretreatment; evaporator /crystalizer sys-tem; solidification system; high and inter-mediate activity process sampling and sam-ple solidification for process control data verification and shipping reporting; filtration systems; domineralization; air and steam supply systems; radioactive resin transfer-and. sampling; pumps; and materials handling equipment.

1971-79 Not engaged in the practice of engineering. .

.1968-70 Douglas United Nuclear, Richland, Washington Engineer - Reactor and Fuels Technology subsection at N-Reactor. (Summer Engineer, 1966-1967.) Performed analysis of fuel thermal. hydraulics for a pressure tube PWR j (N-Reactor) including: two phase flow; thermal balances; heat transfer to single and 2-phase forced convective flow; fuel burnout' margins; vibration; materials con-siderations; full-size loop testing; prima-ry system flow analysis for steady-stater

transient:and accident cases; and LOCA studies.

Also constructed a multi-volume mass and heat transfer model of the N-Reactor con-finement system by finite difference

r-c 4 Donald H. Stevens Page 3 methods, including thermal capacitance de-pendent heat transfer and aerosol mechanics for-time dependent heat and mass transfer to the confinement spray system.

EDUCATION: B.S., Mechanical Engineering, University of Washington, 1966 M.S., Nuclear Engineering, Massachusetts Institute of Technology, 1968 REGISTRATION: Professional Engineer - Pennsylvania (1981)

PUBLICATIONS: Masters thesis: "A Very Intense Pulsed Continuum X-Ray Source," MIT, 1968 D.H. Stevens; D. T. Klinksiek: " Design and Development of a Post-Accident Sampling System,"

presented at the American Power Conference, Chicago, Illinois, April 1981.

I k'

r

gn[ r February 5, 1985 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
Before the Aten.ic Safety and Licensing Board In the Matter of )

)

THE CLEVELAND ELECTRIC ) Docket Nos. 50-440 LILLUMINATING COMPANY, _E_T AL_.

) 50-441

)

(Perry Nuclear Power Plant, )

Units 1 and 2) )

CERTIFICATE OF SERVICE I hereby certify that copies of " Applicants' Motion for

. Summary-Disposition of Issue No. 15," " Applicants' Statement of

'Haterial Facts As.To Which There Is No Genuine Issue To Be

-Heard on Issue No. 15," " Affidavit of Richard A. Pender," and

" Affidavit of Donald H. Stevens," were served this 5th day of February, 1985, by deposit.in the U.S. mail, first class, post-

-age. prepaid, upon'the parties listed on the attached Service >

List,-except for those parties identified by asterisk, who were served by_ hand delivery.

&s'thh Michael A. Swiger

& o &EyA ---

DATED j February 5, 1985 L i

r-  %

g 6. &

' 4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

- Before the Atomic Safety and Licensing Board In the Matter of )

)

'THE CLEVELAND' ELECTRIC ) Docket Nos. 50-440

. ILLUMINATING COMPANY, ET AL. ) 50-441

)

-(Perry Nuclear Power Plant, )

Units 1 and 2) )

SERVICE LIST James P.-Gleason, Chairman Atomic Safety and Licensing 513 Gilmoure Drive Appeal Board Panel Silver Spring, Maryland 20901 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

'Dr. Jerry R.=Kline Docketing and Service Section Atomic Safety and Licensing Board Office of the Secretary U.S. Nuclear. Regulatory' Commission U.S. Nuclear Regulatory Commission Washington,1D.C. 20555 Washington, D.C. 20555 Mr. Glenn O. Bright'

  • Colleen P. Woodhead, Esquire Atomic Safety and Licensing Board Office of.the Executive Legal 4

- U.S. Nuclear Regulatory CommissionL Director Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Alan.S. Rosenthal, Chairman *'Ms. Sue Hiatt Atomic Safety and Licensing OCRE Interim Representative Appeal Board 8275 Munson Avenue U.S. Nuclear Regulatory Commission - Mentor, Ohio 44060 i Washington, D.C. 20555

Dr. W. Reed--Johnson
  • Terry Lodge, Esquire Atomic Safety and Licensing 618 N. Michigan Street, Suite 105

+ Appeal Board Toledo, Ohio 44060

- U.S. Nuclear Regulatory Coma ,sion Washington, D.C. 20555 I Gary J. Edles,. Esquire Donald T. Ezzone, Esquire Assistant Prosecuting Attorney Atomic Safety and Licensing Appeal' Board Lake County Administration Center-U.S. Nuclear Regulatory Commission 105 Center Street

Washington, D.C. 20555 Painesville, Ohio 44077

" Atomic Safety and Licensing John G. Cardinal, Esquire Board Panel Prosecuting Attorney U.S. Nuclear Regulatory Commission Ashtabula County Courthouse Washington, D.C. 20555 Jefferson, Ohio 44047' L

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