ML20245G700

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Rev 8 to Pump & Valve Inservice Testing Program
ML20245G700
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 04/19/1989
From:
DUKE POWER CO.
To:
Shared Package
ML20245G200 List:
References
PROC-890419-01, NUDOCS 8905030213
Download: ML20245G700 (51)
v • d • e


Text

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UNIT 2

(V e) TABLE OF CONTENTS Page  ;

Section Number I. Pump Inservice Testing Program I.1 Introduction I.2 Data Sheets I.3 General Relief Requests I.4 Specific Relief Requests II. Valve Inservice Testing Program-II.1 Introduction II.2 . Table of Abbreviations II.3 Definitions of Testing Requirements and Alternatives II.4 System Data Sheets:

Steam Generator Blowdown Recycle (BB) ............... 1 Auxiliary Feedwater (CA) ............................ 2 Feedwater (CF) ...................................... 3 Diesel Generator Engine Fuel Oil (FD) ............... 4 Refueling Water (FW) ................................ 5 L/7 Component Cooling (KC) .............................. 6 j T

) Radi ation Moni tori ng (MI) . . . . . . . . . . . . . . . . . . . . . . . . . . .

Baron Recycle (NB) ..................................

7 8

Reactor Coolant (NC) ................................ 9 Residual Heat Removal (ND) .......................... 10 Ice Condensor Refrigeration (NF) .................... 11

. Safety Injection (NI) ............................... 12-13 Nuclear Sampling (NM) ............................... 14 Containment Spray (NS) .............................. 15 Chemical and Volume Control (NV) .................... 16 Fire Protection (RF) ................................ 17 Nuclear Service Water (RN) .......................... 18-19 Containment Ventilation Cooling Water (RV) .......... 20 Main Steam Supply to Auxilary Equipment / Turbine Exhaust (SA) .-................................. 21 Main Steam (SM) ..................................... 22 j Main Steam Vent to Atmosphere (SV) .................. 23 Breathing Air (VB) .................................. 24 Annulus Ventilation (VE) ............................ 25 Diesel Generator Starting Air (VG) .................. 26 ,

Instrument Air (VI) .................................

! 27 '

I Containment Purge Ventilation (VP) .................. 28 Containment Air Release and Addition (VQ) ........... 29 i Station Air (VS) .................................... 30

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8905030213 890419..

PDR ADOCK 05000369 p PNU

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. 7- ,- UNIT 2-

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Pade Section Number

> Containment Air Return Exchange and

. . Hydrogen Skimmer (VX) ..........................

31

-Equipment; Decontamination (WE) ...................... 32 Liquid Waste Recycle (WL) ........................... 33 4

' Diesel Generator Room Sump Pump (WN)................. 34 Makeup Demineralized Water (YM) ..................... 35

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' II.5 General. Relief Requests

.II.6 . Specific Relief. Requests-II.7 Cold Shutdown. Justifications t )

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  • r DUKE POWER' COMPANY

- McGUIRE NUCLEAR STATION UNIT.2 i hb, PUMP INSERVICE TESTING PROGRAM ASME SECTION XI, SUBSECTION IWP 1.Q~

. .\

. INTRODUCTION' The inservice testing of ASME Code Class 1,.2 and 3 pumps provided with an emergency power source will be tested as required by Section XI . Subsection IWP, of the ASME.

Boiler and Pressure Vessel Code 1980 Edition, except where specific written relief has

.been granted by the Nuclear Regulatory Commission. .'A. description of the proposed-inservice testing program, as well as specific relief requests from code requirements determined to be impractical, is described in this submittal.

i NOTES:. 1) 'IWP-6240(f). requires the signature of the person or persons-

. responsible for. conducting and. analyzing the test. The dated initials of the person or persons responsible for conducting and; analyzing the test may be used in place of a signature in the record

' " of tests. . Initials shall be construed as signatures to meet the

., intent of IWP.

2) IWP-4110 requires instrument accuracy to be within the limits of Table IWP-4110-1. For vibration,~the acceptable instrument accuracy is tS% of full scale. Presently, the accuracy of the meter being used for vibration measurements is 111%. The present test instrumentation will be upgraded by June 1,1989 to meet the 'IWP
4. bd

.. instrument accuracy requirement. Also,1 vibration measurements will be changed from displacement to' velocity by the above date.

3): After changing to velocity vibration measurements, bearing temperature. measurements will be dropped from our IST program. l

4) Presently,.D/G Room Sump Pumps -(Section I.4E) are not being compared

> to Acceptance Criteria developed in accordance with IWP. Reference values are being determined and changes to our testing procedure will Rev. 8 follow. Full compliance, including relief request, will be in effect

h. by 8/1/89.

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4 I.4 The'following Safety Class 2 and 3 Pumps (see Section I.2 for available instrumentation) will be tested'in accordance with the intent of Subsection IWP

.l.Q of the ASME Code, except where' relief requests haye been written for specific j

V requirements determined to be impractical as described below:

(A) ' PUMPS:-

.0/G Fuel Oil Transfer Pumps (2A, 28)

SAFETY CLASSi 3 FUNCTION: Diesel Generator. Auxiliary Support TEST REQUIREMENTS: . Test pumps in accordance with Subsection IWP BASIS FOR RELIEF: IWP does'not provide appropriate provisions for testing positive displacement pumps.

ALTERNATE TESTING: The Fuel Oil Transfer Pumps are internal gear positive displacement pumps. The performance curve for these-i pumps is'relatively flat. Capacity of these pumps is independent of discharge pressure when operating properly and operating below the' cracking pressure of the pump internal relief valve. Discharge pressure .

will be msasured for information ~ purposes, but will  !

not be compared to any' acceptance criteria. Pumps will be tested'by measuring level rise in the Fuel Oil

' Day Tank and converting this to flowrate. Pump testing is between the levn1'setpoints of the Fuel Oil Day Tank and this gives a run time of approximately 60-75 seconds. The flowrate (Q) will be compared to p

L acceptance criteria established in accordance with Table IWP-3100-2 except the Acceptable Range has been

<- widened:and the High Alert Range increased to allow L for level instrument fluctuations.

I-REV. 8 Acceptable Range: 0.94 to 1.07 Qr Low Alert Range: 0.90 to 0.94 Qr j High Alert Range: 1.07 to 1.10 Qr t 4 Low Required Action Range: <0.90 Qr .I High Required Acti v Range: >1.10 Qr These pumps are designed to produce a flowate of 22 gpm.' The system design flowrate requirement for i the pumps is 11 gpm. This difference provides a comfortable margin in the event a reference value is falsely established that would allow approximately 12%

pump degradation before requiring any action in accordance with IWP. ,

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i 0/G Fuel Oil Storage Tank is monitored to maintain 7x - level required by McGuire Technical Specifications.

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This level ensures adequate NPSH and no suction gauge

.is required.

No lubrication level verification is required for this pump. Lubrication is maintained under our routine preventative maintenance program.

The mechanical condition of the subject pumps will be determined from vibration data to be gathered quarterly. No bearing temperature instrumentation is-installed. OM-6 will.not require bearing temperature measurements.

In addition, monthly Diesel Generatar starting and loading (as required by McGuire Technical Specifications) will assess the hydraulic condition of the subject auxiliary pumps and demonstrates the capability of the individual components to perform

~

their design function.

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O New Page - Rev. 8

(E) PUMPS: D/G Room Sump Pumps (2A2, 2A3, 2B2, 283)

V SAFETY CLASS: 3 FUNCTION: Water removal from Diesel Generator Rooms TEST REQUIREMENT: Test pumps in accordance with Subsection IWP.

BASIS'FOR RELIEF: The D/G Room Sump Pumps are vertical pumps tested by r filling the D/G Room Sump and pumping the sunp down.

No stable system conditions can be obtained due to the

-continuous decrease in sump level. No sucticn pressure, flow, bearing temperature, or lubricant level instrumentation is available.

ALTERNATE TESTING: The D/G f,oom Sump Pumps will be tested for greater than or equal to emergv" y design flow by:

(1) Filling the sump and recording level.

(2) Pumping down the sump and recording both level and pump down time.

An average flow rate will be determined from the time it takes to pump a known volume from the sump. Pumping down the sump takes approximately

(' 60 seconds. An average discharge pressure will j r3 Rev. 8

'() be determined and recorded. The flow rate will be compared with acceptance criteria established per Table IWP-3100-2.

No lubrication level verification is required for this ,

pump. Lubrication is maintained under our routine preventative maintenance program.

No suction pressure instrumentation is required since j this pressure can be calculated from sump level measurements.

The mechanical condition of the subject pumps will be determined from vibration data to be gathered quarterly. No bearing temperature instrumentation is installed. OM-6 will not require bearing temperature i measurements. i O

Rev. 8

McGUIRE - UNIT 2

[ ) -

Quarterly (Q) Testing will be performed at least once per three (3) months.

Refueling Outage (RF) Testing will be performed when the unit is shut down for refueling. Safety valves will be tested periodically per the testing schedule defined in ASME Rev 8 Subsection IW-3510. Testing may be done while in No Mode as well as Modes 3, 4, 5, and 6.

Refueling Outage (RF*) Valve will normally be tested during refueling outages, not to exceed 24 months per Appendix J to 10CFR50.

Refueling Outage (RF#) Valve will normally be tested on a routine basis via a sample valve disassembly program (1 valve from a group of identical valves under similar system conditions). Failure of one valve of the group during a refueling outage will result in all remaining valves of the group being tested during that outage, l

(IV I

Setpoint (SP) Valve will be tested to verify that it will relieve pressure at its specified setpoint.

Testing will be performed per the requirements of IW-3510.

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Page No. 1 04/04/89

- - -x Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

10 - -

2BB-0002B B 2580-1.0 H-04 B ST-Q - -

10 - -

2BB-0003B B 2580-1 0 H-12 B ST-Q - -

10 - -

2BB-0004B B 2580-1.0 H-10 B ST-Q - -

10 - -

2BB-0005A B 2580-1.0 F-02 B ST-Q - -

10 - -

2BB-0006A B 2580-1.0 F-04 B ST-Q -

10 - -

2BB-0007A B 2580-1.0 F-12 B ST-Q - -

10 - -

2BB-0008A B 2580-1.0 F-10 B ST-Q - -

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? age No. 2; l .'~~T 04/04/89

-( ) Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE l TESTING PROCRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM C00R REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

10 - -

2CA-0008 C 2592-1.1 B-11 C MTC-Q - - - - -

2CA-00098 C 2592-1.1 C-05 B ST-Q - -

10 - -

2CA-0010 C 2592-1.1 C-05 C MTC-Q - - - - -

2CA-0011A C 2592-1.1 B-04 B ST-Q - -

10 - -

2CA-0012 C 2592-1.1 B-03 C MTC-Q 2CA-0015A C 2592-1.1 D-03 B ST-Q - -

10 - -

2CA-0018B C 2592-1.1 D-03 B ST-Q - -

10 - -

2CA-0020AB C 2592-1.1 1-10 B ST-Q - -

60 - -

2CA-0022 C 2592-1.1 1-10 C MTO-Q - - - - -

2CA-0026 C 2592-1.1 .I-04 C MTO-Q - -

2CA-0027A C .2592-1.1 J-05 B ST-Q - -

60 - -

2CA-0031 C '2592-1.1 1-07 C MTO-Q - - - - -

,s 2CA-0032B C 2592-1.1 1-08 B ST-Q - -

60 - - '

i ) 2CA-0036AB C 2592-1.0 L-10 B ST-Q - -

60 - -

\- 2CA-0037 B 2592-1.0 K-14 C MTO.C-Q - - -

CS-CA1 -

2CA-00388 B 2592-1.0 J-14 B SI-Q - -

12 - -

2CA-0040B C 2592-1.0 G-14 B ST-Q - -

60 - -

2CA-0041 B 2592-1.0 H-14 C MTO.C-Q - - -

CS-CA1 -

2CA-0042B B 2592-1.0 1-14 B ST-Q - -

10 -

2CA-0044B C 2592-1.0 C-11 B ST-Q - -

60 - -

2CA-0045 B 2592-1.0 C-09 C MTO.C-Q - - -

CS-CA1 -

2CA-0046B B 2592-1.0 D-08 b ST-Q - -

10 - -

2CA-0048AB C 2592-1.0 K-08 B ST-Q - -

60 - -

2CA-0049 B 2592-1.0 H-08 C MTO.C-Q - - -

CS-CA1 -

2CA-0050B B 2592-1.0 G-08 B ST-Q - -

12 - -

2CA-0052AB C '2592-1.0 K-07 B ST-Q - -

60 - -

2CA-0053 B 2592-1.0 H-07 C MTO.C-Q - - -

CS-CA1 -

2CA-0054AC B 2592-1.0 G-07 B ST-Q - -

12 - -

2CA-0056A C 2592-1.0 C-04 B ST-Q - -

60 - -

2CA-0057 B 2592-1.0 C-06 C MTO.C-Q - - -

CS-CA1 -

2CA-0058A B 2592-1.0 D-07 B ST-Q - -

10 - -

2CA-0060A C 2592-1.0 G-01 B ST-Q - -

60 - -

2CA-0061 B 2592-1.0 H-01 C MTO.C-Q - - -

CS-CA1 -

2CA-0062A B 2592-1.0 I-01 B ST-Q - -

10 - -

2CA-0064AB C 2592-1.0 L-04 B ST-Q - -

60 - -

2CA-0065 B 2592-1.0 K-01 C MT0.C-Q - - -

CS-CA1 -

2CA-0066AC B 2592-1.0 J-01 B ST-Q - -

12 - -

2CA-0086A C 2592-1.1 C-14 B ST-Q - -

10 - -

[__\ 10 l 2CA-0116B C 2592-1.1 G-14 B ST-Q - - -

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\_, 2CA-0161C C 2592-1.1 B-12 B ST-Q - -

10 - -

2CA-0162C C 2592-1.1 B-12 B ST-Q - -

10 - -

2CA-0165 C 2592-1.1 C-14 C MTO-Q -

CA1 -

RF# -

2CA-0166 C 2592-1.1 G-14 C MTO-Q CA1 -

RF# -

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04/04/89 L([" sh

-Duke Power Company.

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~ McGuire Nuclear Station PUMP AND VALVE INSERVICE:

. TESTING PROGRAM

. VALVE., 'CL, FLOW FLOW CAT TEST,- TEST RR STROKE TES T .

R.

' DIAGRAM COOR REQ 1D REQ 2 TIME ALTERNATIVES /- E (SEC) REMARKS V

- * * - FEEDWATER 2CF-0017AB'-~F 2591-1.1 K-03 B ST-Q. - -

5 -CS-CF2 -

2CF-0020AB LF '2591-l'.1 K-06' B. ST-Q -- -

5 CS-CF2 -

2CF-0023AB F 2591-1.1 K-09 B. ST-Q - -- 5 CS-CF2 -

2CF-0026AB B 2591-1.1~ H-03 B -ST-Q - -

5 CS-CF1 --

2CF-0028AB .B 2591-1.1 11-06 B ST-Q - -

S' CS-CF1 -

2CF-0030AB LB 2591-1.1 H-09 B ST-Q .

S' CS-CF1 -

2CF-0032AB F' 2591-1.1 K-13 B ST-Q - -

5 CS-CF2 -

2CF-0035AB B: 2591-1.1 H-13 B ST-Q - -

5 CS-CF1 -

2CF-0104ABL B 2591-1.l- K-12 B' ST-Q - -

5 CS-CF4 -

2CF-0105AB- B' 2591-l'.1- K-09 5' CS-CF4 -

B. ST-Q - -

2CF-0106AB -B' 2591-1.1 .K-05 CS-CF4 -

B' .ST-Q - -

5 (2CF-0107AB B- 2591-1.1- K-02 B ST-Q - -

5 CS-CF4 -

2CF-0126B. 'B 2591-1.1 H-11 B ST-Q .

9 CS-CF3 8

. ._. 2CF-0127B B 2591-l'.1 H-08 'B ST-Q - -

9 CS-CF3 8

'2CF-0128BJ B L2591-1.1 H-04 B ST-Q - - 9 .CS-CF3- 8-

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%,,/. 2CF-0129B B 2591'-1,1 H-01 B ST-Q - -

9 CS-CF3 8 2CF-0134A B .2591-1.1 H-12 B ST-Q - -

9 -

3 2CF-0135A B 2591-1.1- G-09 B ST-Q - .

9 - 8 2CF-0136A B 2591-1.1 G-05 B ST-Q - -

9 -

8 2CF-0137A iB 2591-1.1 G-02 B. ST-Q - - 9 - 3 2CF-0151B B 2591-1.1 G-12 B ST-Q - -

9' -

8 E 2CF-0152 B 2591-1.1 F-12 C. MTC-Q - - -

CS-CF5'  ;-

2CF-0153B B".2591-1.1' G-11 B .ST-Q - -

9 -

3 2CF-0154-  : B = -. 2591-1.11 -F-11' C MTC-Q - - -

CS-CF3 -

2CF-0155B B 2391-1,1- G-11 B ST-Q - -

9 - u

.2CF-0156 B' 2591-1.1 F-10 'C MTC-Q CS-CF5 -

2CF-0157B. .B -2591-1.1 G-12 B ST-Q - -

9 - -

2CF-0158 B '2591-1.1 F-12 C MTC-Q - - -

CS-CF5 -

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(_) Duke Power Company McGuire Nuclear Station j

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PUMP AND VALVE INSERVICE l TESTING PROGRAM )

TEST

)

VALVE CL FLOW FLOW CAT TEST TEST RR STROKE R )

i DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

    • DIESEL' GENERATOR ENGINE FUEL OIL 2FD-0092 C 2609-3,0 E-13 C MTO-Q - - - - -

2FD-0104 C 2609-3.1 E-13 C MTO-Q - - - - -

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Page No..-- S' a t- .04/04/89.'

A/: Duke Power Company:

McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL -FLOW FLOW CAT TEST TEST RR STROKE TEST- R DIAGRAM. COOR REQ 1 ' REQ 2 ' TIME ALTERNATIVES / E (SCC)- REMARKS V f

~- ** REFUELING WATER 2FW-0001A B-~2571-1.0- E-11 B- ST-Q - - 10 - -

2FW-0004 B 2571-1.0 D-08 A LT-RF - - -

PASSIVE -

I 2FW-0005 B- 2571-1,0- .C-07 .AC LT-RF - - -

PASSIVE. -

h 2FW-0011 B 2571-1.0 C-02 A LT-RF - - -

' PASSIVE -

2FW-0013. B 2571-1.0- D-02 A. LT-RF - - -

PASSIVE -

L 2FW-0027A -B' 2571-1.0 C-12 B ST-Q - -

30 CS-FF1 -  ;

2FW-0028 -

B 2571-1.0 B C MTO.C-Q -

FW1 --

RF lB: 2571-1.0' E-11 B -ST-Q - -

10 - -

f 2FW-0032B

!2FW-0033A B 2571-E.0 F-11 B~ ST-Q 10 - -

-l 32FW-0049B B 2371-1.0 F-10 B ST-Q - -

10 =

2FW-0052 E 2571-1.0 I-05 C MTO-Q - - -

)s PASSIVE P 2FW-0063- tB '2571-1.0 C-03 AC LT-RF - - - -

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Page No. 6 04/04/89

/~') Duke Power Company (m/ McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM l VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V l

i

60 - -

2KC-0002B C 2573-1.0 C-08 B ST-Q - -

60 - -

2KC-0003A C 2573-1.0 C-07 B ST-Q - -

50 - -

2KC-0005 C 2573-1.0 F-04 C MTO-Q - - - - -

2KC-0008 C 2573-1.0 F-04 C MTO-Q - - - - -

2KC-0011 C 2573-1.0 F-11 C MTO-Q - - - - -

2KC-0014 C 2573-1.0 F-11 C MTO-Q - - - - -

2KC-0018B C 2573-1.0 C-08 B ST-Q - -

50 - -

2KC-0047 8 2573-4.0 L-07 AC MTC-Q LT-RF KC5 -

MT-RF -

2KC-0050A C 2573-1.0 K-07 B ST-Q - -

60 - -

2KC-0051A C 2573-1.0 J-05 B ST-Q - -

10 - -

2KC-0053B C 2573-1.0 K-08 B ST-Q - -

60 - -

2KC-0054B C 2573-1.0 J-10 B ST-Q - -

10 - -

2KC-0056A C 2573-1.1 E-02 B ST-Q - -

60 - -

C 2573-1.1 D-06 B 60 - -

f'^T 2KC-0057A ST-Q - -

2KC-0081B C 2573-1.1 E-13 B ST-Q - -

60 - -

('~') 2KC-0082B C 2573-1.1 D-09 B ST-Q - -

60 - -

2KC-0228B C 2573-1.0 K-08 B ST-Q - -

40 - -

2KC-0230A C 2573-1.0 K-07 B ST-Q - -

40 - -

2KC-0279 B 2573-3.1 K-04 AC MTC-Q LT-RF KC3 -

MT-RF - 4 2KC-0280 B 2573-3.1 D-01 AC MTC-Q LT-RF KC1 -

MT-RF -

2KC-0305B B 2573-3.1 D-14 B ST-Q - -

30 -

l 2KC-0315B B 2573-3.1 L-13 B ST-Q - -

30 - -

2KC-0320A B 2573-3.1 C-10 A ST-Q LT-RF -

15 CS-KC4 -

2KC-0322 B 2573-3.1 C-09 AC MTC-Q LT-RF KC2 -

MT-RF -

2KC-0332B B 2573-3.1 D-01 A- ST-Q LT-RF -

15 CS-KC3 -

2KC-0333A B 2573-3.1 G-01 A ST-Q LT-RF -

15 CS-KC3 -

2KC-0338B B 2573-3.1 D-12 A ST-Q LT-RF -

40 CS-KC2 -

2KC-0340 B 2573-3.1 E-12 AC ST-Q MTC-Q KC4 -

MT-RF -

l 2KC-0424B B 2573-3.1 L-04 A ST-Q LT-RF - 40 CS-KC1 -

2KC-0425A B 2573-3.1 L-06 A ST-Q LT-RF -

40 CS-KC1 -

2KC 0429B B 2573-4.0 K-07 A ST-Q LT-RF -

15 - -

2KC-0430A E 2573-4.0 K-08 A ST-Q LT-RF -

15 - -

2KC-0972 C 2573-1.1 K-08 C SP-RF - -

15 PSIG i

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,Page.No. .7 )

!04/04/89 l Duke Power Company g{, h ; -

+ -McGuire Nuclear Station  !

PUMP AND VALVE INSERVICE' TESTING PROGRAM VALVE CL FLOW . FLOW -' CAT TEST TEST RR STROKE TEST. R- i DIAGRAM; COOR- REQ 1 REQ 2 TIME ALTERNATIVES / .E:

(SEC). REMARKS ' V.

    • RADIATION MONITORING 2MI-5580 ' B '2499-MI7 N/A- A ST-Q LT-RF -

2 - -

'2MI-5581 . B 2499-MI7' - N/A' A ST-Q' .LT-RF -

2 - -

2MI-5582 B 2499-MI7- N/A A ST-Q LT-RF -

-2 - -

-2MI-5583 B 2499-MI7 N/A A ST-Q LT-RF -

2- - -

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04/04/89 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST H DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS .V q l 1

15 - --

-2NB-0262 B 2556-3.0 G-03 AC MTC-Q LT-RF NBl -

MT-RF -

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.. - , . :04/04/89 F )j :

2 Duke Power Company

,}s_,/. McGuire Nuclear Station i .

PUMP AND VALVE INSERVICE j, TESTING PROGRAM VALVE CL- FLOW FLOW CAT TEST TEST RR STROKE TEST- R Dr.AGRAM C00R REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC)- REMARKS V

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10 - -

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2 CS-NC1 -

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Page No. . 10:

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// Duke Power Company (s

McGuire Nuclear. Station-PUMP AND VALVE INSERVICE TESTING PROGRAM'

< VALVE- CL FLOW FLOW CAT TEST TEST' RR' STROKE TEST R

' DIAGRAM- 'COOR REQ 1' REQ 2 ' TIME' ALTERNATIVES / E (SEC) REMARKS V

    • RESIDUAL HEAT REMOVAL-

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  1. .,J Page No.. 11L T 04/04/89;

'Q Duke Power 1 Company-McGuire Nuclear station a~

PUMP AND VALVE INSERVICE

-TESTING PROGRAM

  1. V^LVE- . .CL FLOW FLOW CAT TEST' TEST RR- -STR0KE TEST' R DIAGRAM COOR REQ 1 REQ 2 TIME- ALTERNATIVES / E

-(SEC) REMARKS V

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.04/04/89 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE' CL FLOW .  : FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM- C00R REQ 1 REQ 2 TIME ALTERNATIVES / E M (SEC) REMARKS V j

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Page'No. 13 1 04/04/89-I

'[ s Duke Power Company-McGuire Nuclear Station

PUMP AND VALVE INSERVICE ,

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~ DIAGRAM COOR - REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V lb 2NI-0152B B' 2562-3.0 ,D-06 B ST-Q' - -

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[Page No' . ~ 14' -

'04/04/89 .

M Duke = Power Company. l l

V' ' 'McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE. :CL -FLOW FLOW ' CAT TEST TEST RR . STROKE TEST R

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)1 Page No. 15 04/04/89:

f-'y Duke Power Company 4 ,)

McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REHARKS -V i

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Page No., 16 04/04/89

.?,c ,Y Duke Power Company

'( McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R 3 DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

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McGuire. Nuclear Station

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i Page No. 18 04/04/89 f w, Duke Power Company McGuire Nuclear Station

(' ') PUMP AND VALVE INSERVICE i TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

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l 2RN-0025B C 2574-1.1 C-04 B ST-Q - -

60 CS-RN1 -

i 2RN-0026B C 2574-1.1 G-05 B ST-Q - -

60 CS-RN1 -

j 2RN-0028 C 2574-1.1 J-09 C MTO-Q - - - - -

2RN-0030 C 2574-1.1 E-09 C MTO-Q - - - - -

2RN-0040A C 2574-1.1 1-12 B ST-Q - -

60 - -

2RN-0041B C 2574-1.1 F-12 B ST-Q - -

60 U2 & U1 SIGNAL -

2RN-0042A C 2574-4.0 B-09 B ST-Q - -

60 CS-RN4 -

'2RN-0043A C 2574-1.1 F-12 B ST-Q - -

60 U2 & U1 SIGNAL -

2RN-0063B C 2574-4.0 L-10 B ST-Q - -

60 CS-RN5 -

2RN-0064A C 2574-4.0 L-11 B ST-Q - -

60 CS-RN5 -

,~ 2RN-0068A C 2574-1.1 L-12 B ST-Q - -

2 - -

(s) 2RN-0069A 2RN-0070A C 2574-2.0 C 2574-2.0 K-07 E-06 B

B ST-Q ST-Q 10 60 2RN-0073A C 2574-2.0 I-06 B ST-Q - -

60 - -

2RN-0086A C 2574-2.0 D-12 B ST-Q - -

60 - -

2RN-0089A C 2574-2.0 J-12 B ST-Q - -

60 - -

1 2RN-0103A C 2374-2.1 C-06 B ST-Q - -

2 - -

2RN-0112A C 2574-2.0 I-08 B ST-Q - -

2 - -

2RN-0113 C 2574-2.0 D-13 C MTO-Q RN1 -

RF -

2RN-0114A C 2574-2.1 B-11 B ST-Q - -

2 -

2RN-0117A C 2574-2.0 T-10 B ST-Q - -

2 - -

l D-10 B 60 - a  ;

2RN-0126A C 2574-2.1 ST-Q - -

3RN-0130A C 2574-2,1 C-10 B ST-Q - -

2 -

-j 2RN-0134A C 2574-2.1 C-07 B ST-Q - -

60 - -

2RN-0137A C 2574-2.1 H-07 B ST-Q - -

60 -

2RN-0140A C 2574-2.0 E-14 B ST-Q - -

2 - -

4 2RN-0161B C 2574-1.1 B-12 B ST-Q - -

2 -

l 2RN-0162B C 2574-3,0 J-07 B ST-Q - -

10 - -

l 2RN-0166A C 2574-2.0 I-01 B ST-Q - -

60 - -

2RN-0170B C 2574-3.0 1-01 B ST-Q - -

60 - -

2RN-0171B C 2574-3.0 F-07 B ST-Q - -

40 - -

1 l

2RN-0174B C 2574-3,0 1-07 B ST-Q - -

60 - -

2RN-0187B C 2574-3.0 F-12 B ST-Q - -

60 - -

2RN-0190B C 2574-3.0 J-12 B ST-Q - -

60 - -

2RN-0204B C 2574-3.1 C-05 B ST-Q - -

2 -

2RN-0213B C 2574-3.0 J-08 B ST-Q - -

2 -

/N , 2RN-0214 C 2574-3.0 D-14 C MTO-Q -

RN1 -

RF -

( ,) 2RN-0215B C 2574-3.1 B-11 B ST-Q - -

2 - -

2RN-0218B C 2574-3.0 1-10 B ST-Q - -

2 - -

2RN-0227B C 2574-3.1 E-10 8 ST-Q - -

2 -

2RN-0231B C 2574-3.1 C-10 B ST-Q - -

2 -

_ - - __ . - - - _ _ - - - _ J

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',..... j Page No.~  ;' 19

<[7, g}

, 04/04/89.

Duke Power Company McGuire" Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM-q- .

1

.. VALVE - CL ' FLOW ' FLOW CAT TEST. TEST RR . STROKE TEST R^ j DIAGRAM COORc REQ 1 REQ 2- . TIME ALTERNATIVES /' E (SEC)- REMARKS 'V-u,

~

~ 2RN-0235B' .C ~2574 3.1 E-07 'B' ST-Q - -

60 - -

2RN-0238B _C 2574-3.1 I-07.' B ST-Q - -

60 - -

.2RN-0240B- C 2574-3'.0.

F-13 _B ST-Q - -

2 -

2RN-0252B' .-C 2574-4.0 sE-02 A. ST-Q LT-RF -' 30 CS-RN2 -

2RN-0253A- 'C 2574-4.0 .C-02 A ST-Q LT-RF -

30 CS-RN2 -

2RN-0276A C- 2574-4.0 J-02 A: ST-Q LT-RF -- 30 CS-RN3 -

2RN-0277B 1 C 2592-4.0 -H A ST-Q. -LT-RF .- 30 CS-RN3 -

J2RN-0279B lC 1574-1.0 C-02 B -ST-Q - -

60 --- -

2RN-0296A- 'C 2574-1.1~ .L-13 B ST-Q - -

60 - '-

2RN-0297B C 2574-3.0 L-05' B ST-Q - ' -

60 - -

.l 2RN-0299A' C 1574-1.0 C-02 B ST-Q - -

60 - --

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- i_.-_____m ______.__________._._______._______.___________________J._________..___ __1_ . _ _ .m- _ _ _

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!Page No.t 20'

(:; . j 3 ~ 04/04/89 Duke Power Company L --( j 1

^~' .

. McGuire Nuclear Station PUMP AND VALVE INSERVICE

_ . TESTING PROGRAM h ,CL
FLOW STR0KE TEST -R VALVE FLOW- CAT TEST. TEST -RR U DIAGRAM COOR . REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V-1

- ** CONTAINMENT' VENTILATION COOLING. WATER

.2RV-0032A B'~2604-3.0 K-10 A ST-Q LT-RF -

60 CS-RV1 -

2RV-0033B B 2604-3.0 'K-12 A ST-Q .LT-RF -

60 CS-RV1 --

2RV-0076A B 2604-3.0 C-12; A ~ST-Q LT-RF -

60 CS-RV1 -

2RV-00778 B -2604-3,0< C-10 A ST-Q LT-RF. -

60 CS-RV1 -

i

. 2RV-0079A'- B' 2604-3.0 K-07 A' ST-Q LT-RF- -

.30 - -

2RV-0080B B. 2604-3.0 K-06' 'A. ST-Q

- LT-RF --

30 .

2RV-0101A:- ' B -- 2604-3.0- C-05 A ST-Q LT-RF -

30 - -

.2RV-0102B B 2604-3.0 C-07 A ST-Q - -

30 - -

2RV-0126 B 2604-3.0 B-12 AC MTC-Q LT-RF RV1 -

MT-RF* -

'2RV-0130I B' 2604-3.0' 'J-12 AC MTC-Q LT-RF RV1 -

MT-RF* -

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Page No. 21

( ) '04/04/89 i

/ Duke Power Company McGuire Nuclear Station  !

PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW ' CAT TEST TEST RR STROKE TEST R DIACRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E

, (SEC) REMARKS V

RF# -

2SA-0006~ B 2593-1.2 F-03 C MTO,C-Q - SA1 -

RF# -

2SA-0048ABC B 2593-1.2 E-04 B ST-Q - -- 50 - -

2SA-0049AB B 2593-1.2 F-02 B ST-Q - -

50 - -

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' - ":H Page No'. 22-.
, 1, LO_4/04/89-b.E Duke ~ Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM

. VALVE- CL = FLOW..- FLOW ' CAT TEST - TEST RR. . STROKE TEST ~ R DIAGRAM . C00R 2 ' REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS = V

    • . MAIN STEAM-2SM-0001AB B 2593-1.0_ K-13 B ST-Q ' - -

5~ CS-SM1 -

2SM-0003AB .-B 2593-1.0' H-13 '. B ST-Q - - -

5 CS-SMI .

.-2SM-0005AB B .2593-1.0 I-14 B ST-Q - -

5 CS-SM1 -

!2SM-0007AB'.B -2593-1.0 C-14 B'- ST-Q - -

5 -CS-SM1 - 4

'2SM-0009AB. B .2593-1.0 J-13B ST-Q - - -

5 CS-SM2 -

2SM-0010AB B '2593-1.0 .G-13 B -~ 5 CS-SM2 -

ST-Q -

2SM-0011AB B 2593-1.0 I-13 B. ST-Q - -

5 CS-SM2 ' -

2SM-0012AB 'B 2593-1.0l C-13 B ST-Q

~- - -

-5 CS-SM2 -

I '

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= -_ __ _

_s ~Page No. 23

( ) 04/04/89 N- '

Duke Power Company

.McGuire Nuclear Station PUMP AND VALVE INSERVICF TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

60 - -

2SV-0002 8 2593-1.3 K-06 C SP-5Y - - -

1170 PSIG -

2SV-0003 B 2593-1.3 K-07 C SP-5Y - - -

1190 PSIG -

2SV-0004- B 2593-1.3 K-09 C SP-5Y - - -

1205 PSIG -

f 2SV-0005 B 2593-1.3 K-11 C SP-5Y - - -

1220 PSIG -

2SV-0006. B 2593-1.3 K-12 C SP-5Y - - -

1225 PSIG '

2SV-0007ABC B 2593-1,3 G-05 B ST-Q - -

60 - -

2SV-0008 B 2593-1.3 E-06 C SP-5Y - - -

1170 PSIG -

2SV-0009 B 2593-1.3 E-07 C SP-5Y - - -

1190 PSIG -

2SV-0010 B 2593-1.3 E-09 C SP-5Y - - -

1205 PSIG -

2SV-0011 B 2593-1.3 E-11 C SP-5Y - - -

1220 PSIG -

2SV-0012 B 2593-1,3 E-12 C SP-5Y - - -

1225 PSIG -

2SV-0013AB B 2593-1.0 L-04 B ST-Q - -

60 - -

rS 2SV-0014 C 2593-1.0 K-05 C SP-5Y - - -

1170 PSIG -

( ')

2SV-0015 2SV-0016 B 2593-1.0 B 2593-1,0

'K-07 K-09 C

C SP-5Y SP-5Y 1190 PSIG 1205 PSIG 2SV-0017 B 2593-1.0 K-10 C SP-5Y - - -

1220 PSIG -

2SV-0018 B 2593-1.0 K-12 C SP-5Y - - -

1225 PSIG -

2SV-0019AB B 2593-1.0 G-05 B ST-Q - -

60 - -

2SV-0020 B 2593-1.0 E-05 C SP-5Y - - -

1170 PSIG -

2SV-0021 B 2593-1.0 E-07 C SP-5Y - - -

1190 PSIG -

2SV-0022 B 2593-1.0 -E-09 C SP-5Y - - -

1205 PSIG -

2SV-0023 B 2593-1.0 E-10 C SP-5Y - - -

1220 PSIG -

2SV-0024 B 2593-1.0 E-12 C SP-5Y - - -

1225 PSIG -

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1

-Page No. 24 04/04/89

[3 Duke Power Company

'() ~ McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST. TEST RR STROKE TEST R  !

l DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V ]

1

15 - -

2VB-0050 B 2605-3.1 E-04 AC- MTC-Q LT-RF VB1 -

MT-RF* - ,

i n

b 1

1 V, i

Page No. 25 04/04/89 Duke Power Company 9' McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM I

VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST E DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / f ,

(SEC) REMARKS V

15 - -

2VE-0006B B 2564-1 G-04 A ST-Q LT-RF -

15 - -

2VE-0008A B 2564-1 J-02 B ST-Q - -

20 - -

2VE-0010A B 2564-1 H-03 A ST-Q LT-RF ~

15 - -

2VE-0011 B 2564-1 H-03 AC LT-RF - - -

PASSIVE -

O S

Page No. 26 6 04/04/89 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TESI R DIAGPAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V f'

    • DIESEL GENERATOR STARTING AIR 2VG-0061 C 2609-4.0 K-02 B ST-Q -

VG1 -

SEE RELIEF -

2VG-0062 C 2609-4.0 T-02 B ST-Q -

VG1 -

SEE RELIEF -

2VG-0063 C 2609-4.0 I-02 B ST-Q -

Vol -

SEE RELIEF -

l 2VG-0064 C 2609-4.0 H-02 B ST-Q -

VG1 -

SEE RELIEF -

2VG-0065 C 2609-4.0 F-02 B ST-Q -

VG1 -

SEE RELIEF -

2VG-0066 C 2609-4.0 E-02 B ST-Q -

VG1 -

SEE RELIEF -

2VG-0067 C 2609-4.0 C-02 B ST-Q -

VG1 -

SEE RELIEF -

2VG-0068 C 2609-4.0 C-02 B ST-Q -

VG1 -

SEE RELIEF -

2VG-0115 C 2609-4.0 K-09 C MTO-Q - - - -

C 2609-4.0 - -

2VG-0116 H-09 C MTO-Q - - -

2VG-0117 C 2609-4.0 F-09 C MTO-Q - - - -

C 2609-4.0 2VG-0118 C-09 C MTO-Q i

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Page No. 27 04/04/89

7 w)

L Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

    • INSTRUMENT AIR 2VI-0040 B 2605-1.3 J-13 AC MTC-Q LT-RF V12 -

MT-RF* q 2VI-0124 B 2605-1.2 B-04 AC MTC-Q LT-RF VII -

MT-RF* -

2VI-0129B B 2605-1.3 J-11 A ST-Q LT-RF -

15 - -

l 2VI-0148B B 2605-1.2 E-03 A ST-Q LT-RF -

15 - -

2VI-0149 B 2605-1.2 E-05 AC MTC-Q LT-RF VII -

MT-RF* -

2VI-0150B B 2605-1.2 .C-02 A ST-Q LT-RF -

15 - -

2VI-0160B B 2605-1.3 D-11 A ST-Q LT-RF -

15 - -

2VI-0161 B' 2605-1.3 D-13 AC MTC-Q LT-RF VI2 -

MT-RF* -

l 2VI-0362A B 2605-1.2 D-04 A ST-Q LT-RF -

15 - -

,IV u- ,

e______________

i j-L 'Page No. 28

,^) 04/04/89 Duke Power Company

! - (\ 7 McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE- CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM C00R REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

.2VP-0011B B 2576-1 J-09 A ST-Q LT-TS VP1 3 ST-AS REQ'D 8 2VP-0012A B. 2576-1 1-08 A ST-O LT-TS VP1 3 ST-AS REQ'D 8 2VP-0013B B 2576-1 'I-09 A ST-Q LT-TS VP1 3 ST-AS REQ'D 8 2VP-0015A B 2576-1 F-08 A ST-Q LT-TS VP1 3 ST-AS REQ'D 8 2VP-0016B B 2576-1 F-09 A ST-Q LT-TS VP1 3 ST-AS REQ'D 8 LT-TS 8 f)

L/

2VP-0017A 2VP-0018B B 2576-1 B 2576-1 B-07 A B-06 A ST-Q ST-Q LT-TS VP1 VP1 3

J ST-AS REQ'D ST-AS REQ'D d 2VP-0019A B 2576-1 B-08 A ST-Q LT-TS VP1 3 ST-AS REQ'D 3 2VP-0020B B 2576-1 B-09 A ST-Q LT-TS VP1 3 ST-AS REQ'D 3 i

i

g . . _ _ _ - - - _ - _ - _

1 i

1 Page No. 29 04/04/89 {

Duke Power. Company

\m, /~~')\ - McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V
    • . CONTAINMENT AIR RELEASE AND ADDITION 2VQ-0001A B 2585-1.0 J-04 A ST-Q LT-RF -

3 - -

2VQ-0002B B 2585-1.0 J-06 A ST-Q LT-RF -

2 -

8 2VQ-0005B B 2585-1.0 E-06 A ST-Q LT-RF. -

2 -

8 2VQ-0006A B 2585-1.0 E-03 A ST-Q LT-RF -

2 -

8

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[k Page No. 30 Cf 04/04/89 Duke Power Company ,

McGuire Nuclear Station l PUMP AND VALVE INSERVICE I TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STR0KE' TEST R DIAGRAM C00R REQ 1- REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS- V

15 ' - -

2VS-0013 B 2605-2.2 .H-08 AC MTC-Q LT-RF VS1 -

MT-Rt* -

( .

J l

I

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g- 1 Page No. 31 04/04/89

(~'g Duke Power Company

. '(j McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM  ;

VALVE .CL FLOW F1.0h i' It iKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / .

(SEC) REMARKS V

2VX-0001A B 2557-1 1-03 B ST-Q - -

60 - -

2VX-0002B B 2557-1 I-12 B ST-Q - -

60 - -

2VX-0030 B 2557-I J-03 AC MTC-Q LT-RF VX1 -

MT-RF -

2VX-0031A B 2557-1 J-13 A ST-Q LT-RF -

2 - -

2VX-0033B B 2557-1 J-12 A ST-Q LT-RF -

2 - -

2VX-0034 B 2557-1 K-12 A LT-RF - - -

PASSIVE -

2VX-0040 B 2557-1 K-03 A LT-RF - - -

PASSIVE -

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Page'No. 32

/S - 04/04/89 Duke Power Company

. (_) - McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM FLOW CAT TEST TEST RR STROKE TEST R j VALVE CL FLOW DIAGRAM COOR REQ 1 REQ 2- TIME ALTERNATIVES / E i (SEC) REMARKS V

    • EQUIPMENT DECONTAMINATION 2WE-0013 B 2568-1.0 E-08 A LT-RF - - -

PASSIVE -

2WE-0023 B 2568-1.0 E-09 A LT-RF - - -

PASSIVE -

I

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Page No. 33 i f-~s 04/04/89 j Duke Power Company

~

) ',

{

McGuire Nuclear Station l PUMP AND VALVE INSERVICE {

TESTING PROGRAM '

VALVE CL FLOW FLOW CAT TEST TEST RR STR0K2 TEST f:

DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNA.IVES/ E (SEC) REMARKS V

10 - -

2WL-0002A B 2365-1.1 K-13 A ST-Q LT-RF -

10 - -

2WL-0024 B 2565-1.1 J-14 AC MTC-Q LT-RF WL2 -

MT-RF* -

2WL-0039A B 2565-1.1 J-05 A ST-Q LT-RF -

10 - -

2WL-0041B B 2565-1.1 K-05 A ST-Q LT-RF -

10 - -

2WL-0064A B 2565-1.0 J-03 A ST-Q LT-RF -

15 - -

2WL-0065B B 2565-1.0 K-05 A ST-Q LT-RF -

15 - -

2WL-0264 B 2565-1.0 J-02 AC LT-RF - - -

PASSIVE -

2WL-0321A B 2565-7.0 I-05 A ST-Q LT-RF -

15 - -

2WL-0322B B 2565-7.0 H-04 A ST-Q LT-RF -

15 - -

i 2WL-0385 B '2565-7.0 J-05 AC MTC-Q LT-RF WL3 -

MT-RF* -

2WL-0466 E 2565-1.0 G-13 C MTC-Q -

WL1 -

RF -

2WL-1301B B~ 2565-1.0 G-03 A ST-Q LT-RF -

10 - -

2WL-1302A B 2565-1.0 E-04 A ST-Q LT-RF -

10 - -

/,s\

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\

e Page No.

i fs 04/04/89 34

) l

.( i Duke Power Company

! 2 McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / E (SEC) REMARKS V

2WN-0005 C 2609-7.0 K-11 C- MT0.C-Q - - - - -

2WN-0007 C 2609-7.0 J 11 C MTC-Q - - - - -

2WN-0011 C 2609-7.0 F-11 C MTO.C-Q - - - - -

> 2WN-0013 C 2609-7.0 E-11 C MTO.C-Q - - - - -

2WN-0015 C 2609-7.0 D-11 C MTC-Q - - - - -

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Page No. 35 04/04/89

! ; /~'%

Duke Power Company

\s_,/ McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES / T.

(SEC) REMARKS V l

    • MAKEUP DEMINERALIZED WATER 2YM-0115B B 1601-2.4 C-09 A ST-Q LT-RF -

15 - -

2YM-0116- B 1601-2 4 C-04 AC MTC-Q LT-RF YM1 -

MT-RF* -

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McGUIRE - UNIT 2 f).

Q %/ ~

RELIEF / JUSTIFICATION: RR-KC3 VALVE: 2KC-279 FLOW DIAGRAM: MC-2573-3.1 1

-CATEGORY: A,C CLASS: B FUNCTION: Provides containment isolation and prevents overpressurization of line between 2KC-424B and 2KC-425A, TEST REQUIREMENT: Verify valve seats on flow out of containment.

BASIS: The system design does not provide-a means of verifying valve closure upon flow reversal.

-ALTERNATE. TESTING: -Valve will be verified shut by leak test performed in. Rev 8 accordance with Appendix J.

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Revision 8

f l, V ,7 McGUIRE - UNIT 2 I

l ,,

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', RELIEF / JUSTIFICATION: RR-NI4 VALVE: 2NI-81, 2NI-70, 2NI-59, 2NI-93

' FLOW DIAGRAM: MC-2562-2.0, MC-2562-2.1 CATEGORY: A,C CLASS: A FUNCTION: Opens on flow from the NI cold leg accumulator to the Reactor Coolant System.

L.

' TEST.. REQUIREMENT: Full stroke. exercise quarterly.

BASIS: Valves cannot be full or partial stroked during power operation since the accumulator pressure is $600 psig Rev 8 >

and cannot overcome RCS pressure. During cold t shutdown exercising these valves could result in a low temperature overpressurization of the RCS. There is insufficient instrumentation to test valves individually.

f- y ' ALTERNATE TESTING: Valves will be partial stroked during cold shutdown,  !

(j but not more often than once per nine months. Valves ,

will be ful1 stroked at refueling by sample disassembly or other NRC accepted means. Valves will be leak tested.in accordance with Technical Specifications.

Revision 8

. . - . - - . . - _ . _ _ _ . - - - - _ . - . - - . _ - - _ _ _ . . . - __ . - _ . _ ___x h

I i

McGUIRE - UNIT 2 A

N)

RELIEF / JUSTIFICATION: RR-NI9 VALVE: 2NI-128, 2NI-159, 2NI-160, 2NI-156, 2NI-124, 2NI-157 l FLOW DIAGRAM: MC-2562-3.0 i CATEGORY: A,C Rev 8 'l CLASS: B FUNCTION: Provide containment isolation TEST REQUIREMENT: Verify proper valve movement once per three months.

BASIS: Valves cannot be full or partial stroked during power operation since the safety injection pumps cannot discharge into the RCS at operating pressure. During cold shutdown, these valves cannot be full or partial stroked since this could result in low temperature overpressurization.

ALTERNATE TESTING: Valves will be cycled during refueling by sample i

, ?N disassembly or other NRC accepted means. Valves will "s_,) be leak tested in accordance with Tech Spec 4.4.6.2.2.

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RELIEF / JUSTIFICATION: RR-nil 0 VALVE: 2NI-165, 2NI-167, 2NI-169, 2NI-171 FLOW OIAGRAM: MC-2562-3.1

- CATEGORY: A,C

' CLASS: - A FUNCTION: SI discharge check valves TEST REQUIREMENT: Full stroke exercise quarterly.

BASIS: Valves cannot be cycled during power operation since I the'SI pumps cannot overcome RCS pressure to permit l

. flow through the valves. During cold shutdown ,

exercising these valves could result. in low '

temperature overpressurization.

ALTERNATE TESTING: Valves will be cycled during refueling by sample disassembly or other NRC accepted means. Valves will- Rev 8 be leak tested in accordance with Tech Spec 4.4.6.2.2.

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RELIEF / JUSTIFICATION: RR-NI12 VALVE: 2NI-129, 2NI-125, 2NI-134, 2NI-126 FLOW OIAGRAM: MC-2562-3.0 CATEGORY: A,C Rev 8 CLASS: A FUNCTION: Opens on flow from the ND system to the NC Hot Legs.

TEST REQUIREMENT: Full stroke quarterly.

BASIS: ND pumps do not develop enough discharge pressure to overcome RCS pressure at power operation.

. Instrumentation is not present to measure individual flows.

' ALTERNATE TESTING: Valve will be partial stroke exercised during cold shutdown, but not more often than once per nine months. Valves will be fully stroke exercised at f refueling by sample disassembly or other NRC accepted

! means. Valves will be leak tested in accordance with I E Technical Specifications.

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RELIEF / JUSTIFICATION: RR-VG1 VALVE: 2VG-61, 2VG-62, 2VG-63, 2VG-64, 2VG-65, 2VG-66, 2VG-67, 2VG-68 FLOW OIAGRAM: MC-2609-4.0 CATEGORY: B CLASS: C FUNCTION: Starting air solenoid control valves TEST REQUIREMENT: Verify valve operability every three months.

BASIS: Direct observation of valve movement is impossible.

This valve is automatically opened when the diesel generator engine is started. The valve vill then close after the engine is started. Failure of this valve to perform. its required function should be indicated by the diesel's performance when it is tested during refueling. The monthly diesel testing

,rx does not ensure all the valves are operating properly.

Since the refueling diesel test starts the diesel in a Rev 81

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degraded condition, it is not desired to perform this quarterly.

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ALTERNATE TESTING: Valves will be considered to be functioning properly if the diesel's starting time is within Tech Spec limits during refueling testing. ,

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RELIEF / JUSTIFICATION: CS-CF3 VALVE: 2CF-129B; 2CF-1288; 2CF-127B; 2CF-1268 Rev 8 FLOW DIAGRAM: MC-P591-1.1 CATEGORY: B j

CLASS: B FUNCTION: Opens to provide startup feedwater supply to the steam generators.

TEST REQUIREMENT: Cycle and time valve once per three months.

BASIS: Cycling valve during power operation could induce unwanted transients in steam generators. This would result in an increase in flow to the main feedwater nozzles causing vibrations in the preheater section of the steam generators.

ALTERNATE TESTING: Valve will be cycled and timed during cold shutdown.

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RELIEF / JUSTIFICATION: CS-NV12 VALVE: 2NV-150B, 2NV-151A FLOW DIAGRAM: MC-2554-2.0 CATEGORY: B CLASS: B FUNCTION: Isolation valve for centrifugal charging pump miniflow to VCT.

TEST REQUIREMENT: Full stroke exercise quarterly BASIS: If valve fails in the closed position, the l

l recirculation flow path for the centrifugal charging

! pumps is isolated.

ALTERNATE TESTING: Valve will be cycled and timed during cold shutdown.

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- RELIEF / JUSTIFICATION: -CS-NV13

.- VALVE:- 2NV-265B FLOW DIAGRAM: HC-2554-3.1 CATEGORY: B .

CLASS: B n FUNCTIOM: Isolates the Boric Acid Tank from the suction of the Centrifugal Charging Pumps.

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-TEST REQUIREMENT:

Full stroke exercise quarterly. j

- BASIS: If.the valve is. opened during power operation, residual boric acid could be introduced into the Reactor Coolant System causing a transient.  !

ALTERNATE TESTING: Valve will be cycled and timed during cold shutdown.

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