ML18037A360
| ML18037A360 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/07/1981 |
| From: | Schmidt K NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML17053C773 | List: |
| References | |
| NES-81A0416, NES-81A416, NUDOCS 8108140368 | |
| Download: ML18037A360 (190) | |
Text
NES 81A0416 NINE MILE POINT UNIT 1 SECTION'- XI"PUMP AND" VALVE
~
INSERVICE TESTING PROGRAM PLAN BOOK Prepared for NIAGARA MOHAWK POWER CORPORATION Syracuse, New York I,'ON'il'MLLiI.III,'Ol 7 ItALI ONLY IF THlS STAMP lS REO NUCLEAR ENERGY SERVICES, INC.
Danbury, Connecticut 0681p Rev. No.'ate 6/30/78 Prepared by I g 12/29/78 Approved by 12/14/79 Mg of Proj's M r ISI .Eng 12/31/80 QA Mgr 6/)2/8]
C' 8i0807' 8i08140368 05000220 LI 4P
=PDR,. ADOCK
' '~DR NUCt EAR ENBACV SKRV!CES.'NC.
RECORD OF REVI'SION I 81A0416 Rev Date Description Reason Prepared Approved No by by 12/29/78 See CRA 564 NMPC Comments 12/14/79 See CRA 1132, NMPC Comments.
Corrections to Plan.
Reflect as built data. CRA-1132 1 2/31 /8 See CRA 1653 NRC comments from LO/80 meeting; complete'ocument revision and format changes.
6/iz/S> Extensive Revision Zncorporate Sec CRA 1903 NRC and NMPC comments.
gg NUCLEAR EhFPGY SERVtZFS. INC.,
DpCUMENl Np 81 0416 NUCLEAR ENERGY SERVICES, INC.
PAGE ~OF~
TABLE OF CONTENTS
~Pa e
- l. Introduction and Bases
- 2. Test Plan Description
- 3. Pump and Valve Inservice Testing Program Book 3.1 Pump and Valve List 3.2 'alve Relief Requests 3.3 Test Schedules 3.0 General Testing Procedures 3.5 Records 3.6 Field Test Procedures
- 0. Appendices A Pump and Valve List B Valve Relief Requests C Test Schedules D General Test Procedures E Records F Field Test Procedures FORM ONES 205 2/80
DpCUMENT Np 81A0416 NUCLEAR ENERGY SERVlCES, INC.
PAGE 4 OP~
- 1. INTRODUCTION AND BASES This Program Book has been prepared to fulfillthe Pump and Valve Inservice Testing requirements for the Nine Mile Point Nuclear Station Unit 1 operated by Niagara Mohawk Power Corporation.
The 1970 and later editions of ASME Code,Section XI incorporates the requirements for operational testing of certain pumps and valves within a nuclear power plant; The Code of Federal Regulations, under 10 CFR 50.55a, requires that the first pump and valve test period be initiated at the start of the next regular 00 month period in a series of such periods beginning at the start of facility commercial operation. The next 00 month period has been established to start in December, 1979 for Nine Mile Point Unit 1, which dictates that the Pump and Valve Testing Program be submitted to NRC by 3une 1979.
According to 10 CFR 50.55a, the edition of the Code applicable to the Pump and Valve Plan would be the one in effect 6 months prior to the start of the next 00 month period. However, as of this writing, the 1975 Summer Addenda is the latest edition of the code endorsed. by the NRC. Accordingly, the plan complies to the edition of the code currently approved by the NRC and will be revised, as necessary, to meet the requirements of the new edition, as they are received and endorsed by the NRC.
I It should be noted that Nine Mile Point Unit 1 was designed and constructed prior to the adoption of the ASME Code. As a result, certain examinations stipulated by the Code cannot be performed since the plant system and component design does not accommodate them. All pumps and valves that cannot be tested to the full extent of Section XI requirements, due to location, function, design and/or instrumentation, are identified and the reasons for noncompliance fully described using the'tandard formats recommended by the NRC in the "Guidance for Preparing Pump and Valve.
Testing Program Descriptions and Associated Reiief Requests Pursuant to 10 CFR 50.55a(g)" attached to their letter of January 5, 1973 to Niagara Mohawk.
FORM 0 NES 205 2/80
0
'I i I
'OCUMENT NO Slap PAGE 5 OF
~
NUCLEAR ENERGY SERVICES, INC.
The classification is basically provided by Part 50.2(v) of Title 10 of the Code of Federal Regulations for for Quality Group A and by NRC Regulartory 1.26 (Revision 3, February 1976) for Quality Groups B and C.
This Program Book is self contained. Included are instructions for setting up a Section XI Pump and Valve testing schedule and for the integration of the Section XI requirements with the plant Technical Specifications Suveillance testing tasks. The pumps and valves selected are listed in standard formats and reliefs which are detailed in the Relief Request sheets. Listings of general pump and valve testing procedures and component-specific field test procedures as well as a description of the recording requirements are provided.
FORM 0 NES 205 2/SP
C DOCUMENT NO 81A0416 PAGE OF NUCLEAR ENERGY SERVICES, INC.
- 2. TEST PLAN DESCRIPTION According to 10 CFR 50.55a(g), the Section XI Pump and Valve Inservice Testing
'I Program shall be initiated at the start of the next regular 00 month period subsequent to September 1, 1976, in a series of such, periods beginning at the start of the facility commercial operation. The next such per iod has been established to start in December, 1979 for Nine Mile Point Unit l.
This Plan has been prepared in accordance with the requirements of the ASME Section XI, 1970 Edition, up to and including 1975 Summer Addenda, the latest endorsed by the NRC. The Plan shall be revised to comply to the code currently approved by the NRC prior to its implementation in December 1979 and shall be in effect for the first 20 month period; The Plan shall be updated thereafter every 20 months to the edition of the code in effect prior to the start of each 20 month period.
The requirements and record formats for inservice testing of Class 1, 2, and 3 (coresponding to Quality Group A,.B, and C respectively) pumps and valves installed at Nine Mile Point Unit 1 have been defined per Section XI, Subsections IWP and IV/V, as well as per NRC recommendations in "Guidance for'reparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10 CFR 50.55a(g)".
Beyond the code, to meet with NRC requirements, during cold shutdowns, valve testing need not be performed more often than once every three months for category" A, B and C valves. Inservice testing will commence within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after cold shutdown is achieved, but no later than 08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after cold shutdown, and continue until either all tests are complete or the plant is ready to return to power.
The integration of 'the Section XI Pump and Valve Testing requirements with the existing plant maintenance and surveillance programs has received primary consideration in the preparation of this Plan. This will assure elimination of duplication of effort and thus reduce the impact on manpower requirements, exposure rates and scheduling that would be caused by the introduction of a new parallel but separate program. To that goal, existing pump and valve procedures were reviewed FORM n NES 205 2/80
r DOCUMENT NO 81A0416 PAGE OF NUCLEAR ENERGY SERVICES, INC.
and adapted with appropriate modifications, and new procedures written in similar formats where no existing ones could be used. Thus, in most cases, because of unification of the plant's Technical Specification surveillance testing requirements with the Section XI Pump and Valve Testing needs, one test activity on the components will achieve satisfactory compliance in both programs.
The specific Section XI requirements have been summarized in General Testing Procedures, which also include forms to be used to summarize pump and valve testing status and.all supporting documentation. By reference, component-specific Field Test Procedures are part of the General Test Procedures. The Field Test Procedures are the sole documents needed to set up, perform and record the actual field testing and have been modified to accommodate all special requirements defined in the General
., Test Procedures.
The General Test Procedures and all attached forms are primarily designed for program control, analysis and comparison, establishment of reference values, and documentation compliance. Test data, wherever required to be entered, will be transferred from data sheets used in the Field Test Procedures. The results of all analyses shall be reflected back in the "Test Results" section of the Field Test Procedures. All corrective action (repair or replacement of components) shall be initiated by filling out a 0/ork'Request (WR) form as required by the Field Test Procedure.
FORMCNES205 2/80
J, DpCUMENT Np 81A0416 NUCLEAR ENERGY SERVICES, INC.
PAGE E GF~
- 3. PUMP AND VALVE INSERVICE TESTING PROGRAM BOOK The following sections comprise the Nine Mile Point Unit 1 Pump and Valve Inservice Testing Program Book and are discussed in detail in their corresponding Appendices.
3.1 PUMP AND VALVE LIST Addressed in the Program are Quality Group A, B, and C pumps that are provided with an emergency power source and all safety-related Quality Group A, B, and C valves. Safety-related components are those pumps and valves necessary to safely shut down the plant or mitigate the consequences of an accident. Quality Group A, B, and C system boundaries have been established in accordance with Niagara Mohawk Power Corporation Production Plant Engineering DP 020 Mechanical Q-List.
Appendix A identif ies the selected pumps and valves with all additional F
information, including reiief requests, required by the "NRC Staff Guidance".
3.2 VALVE RELIEF REQUESTS Appendix B includes detailed information to support requests for relief from testing requirements for each affected valve. Accessibility, high radiation level, high temperature, lack of instrumentation, impractibility of testing during plant operation are examples of relief bases.
3.3 TEST SCHEDULES Detailed pump and valve testing schedules are presented in Appendix C. The schedules are for a 20 month interval starting in December 1979 through August 1981. "Other information such as parameters to be tested, applicable General Test Procedures and Fieid Test Procedures are also incorporated.
FORM 0 NES 205 2/80
DOCUMENT NO PAGE E OF NUCLEAR ENERGY SERVICES, INC.
3.0 GENERAL TESTING PROCEDURES NES has prepared general testing procedures for Section XI requirements for pumps and each category or type of valve specified. Appendix D presents the General Testing Procedures to be used in the Nine Mile Point Unit l Pump and Valve Testing Program in conjunction with component-specific Field Test Procedures.
3P5 RECORDS Appendix E discusses the Section XI recordkeeping and documentation require-ments for the Pump and Valve Testing Program.
3P6 FIELD TEST PROCEDURES All pump- and valve-specific Field Test Procedures are incorporated in Appendix F. These procedures are either existing Nine Mile Point testing procedures, with minor modifications and additions as necessary, or new procedures written in similar format to satisfy Section XI requirements not accommodated by existing procedures. These Field Test Procedures are to be used in the actual testing of components.
h FORM INES 205 2/80
1 DOCUMENT NO 81A0416 4
PAGE Z 1 OF 37 NUCLEAR ENERGY SERVICES, INC.
APPENDIX A PUMP AND YALVE LIST FORM ONES 205 2/80
81A0416 DOCUMENT NO PAGE OF NUCLEAR ENERGY SERVICES, INC.
PUMP AND VALVE LIST The lists for safety-related Quality Group A, B, and C pumps provided with an emergency power source and safety-related Quality Group A, B, and C valves are presented in this Appendix. The standard format recommended by the NRC Staff in their "Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10 CFR 50.55a(g)" has been used to provide the required information.
In the pump list, the test parameters to be measured and the test frequency are identified. Footnotes '1 through 7 refer to deviations and exceptions to the code requirements and are further discussed below:
- l. For pumps with constant speed drives, speed is not measured since test will be performed at nominal motor nameplate speed as allowed by Section XI, IWP-3100.
- 2. For water sources with essentially constant water levels, inlet pressure P.
1 will not be measured. The water level may be used instead of P. while establishing and verifying Reference 'Data sets and as information during subsequent'test analysis.
3.: For. fixed resistance systems, it is not required to measure differential pressure as the flow rate is being measured as allowed by Section XI, IWP-3100.
Conversely, the flow rate need not be measured if the diff rential pressure is recorded. For constant level water sources, the outlet pressure may be assumed to represent the differential pressure.
- 5. Bearing temperatures are not measurable for submerged oumps where the pumped fluid is used at the bearing cooler. These pumps are not provided'ith built-in bearing temperature measuring devices.
FORM 5 NES 205 2/80
4 DOCUMENT NO SM0416 A
a pAGE NUCLEAR ENERGY SERV(CES, INC.
~OP'.
In view of satisfactory pump surveillance testing performance in the past, quarterly inservice testing is considered to be adequate. 'iquid Poison pumps and the Diesel Cooling Raw Water pumps will be tested on a monthly basis as required by Section XI, IWP-3000.
- 7. On all pumps, bearing temperatures are measured once a year as stipulated by Section XI, IWP-3300 except when not possible as specified in Note (5).
- 8. Constant P. assumed for Core Spray Topping, as the Core Spray and Core 1
Spray Topping pumps are run simultaneously in series.
All relief requests from valve testing requirements are documented in the NRC-recommended standard formats in Appendix B.
FORM ¹NES 205 2/80
4 jl DpCUMENT Np 81A0416 a
PAGE 4 QF 37 NUCLEAR ENERGY SERVICES, INC.
TABLE 1 ABBREVIATIONSUSED IN VALVELIST
~Valve T e Normal Position G Gate/Globe 0 Open R Relief C Closed SC Swing Check LO Locked Open E Explosive LC Locked Closed Actuator T e MO-AC AC current Motor Operated MO-DC DC current Motor Operated AO Air-piston Operated EM Electro-Mechanical SA Self-Actuated AD Air-Diaphram M Manual E Explosive Test Re uirement LRT Leak Rate Test ET Exercising Test (including stroke time, unless otherwise noted)
ET/P Part-stroke Exercising Test PIT Position Indicator Test SRT Safety/Relief Test XT Explosive Test FST Fail Safe Test FORM ONES 205 2/80
0 TABLE 2 z
m LIST OF PUMPS FOR INSERVICE TESTING CO CI tA Quality Measured Parameter Field Test V.
O System Core Spray Pump ID P R ID 1 1 1, 112 18007 Group Freq.
Q6 N p.
2 3 6PQ X,X Tb 5
Proc. No.
Nl-ST-Q 1 Zi 121, 122 z C
n Core Spray ill, 112 18007 B Q6,7 x x x Nl-ST-Q 1 Topping 121, 122 m m
Containment 111, 112 18012 B Q6 2 3 x x 5 Nl-ST-Q6 Q Spray 121; 122 CO m
Cont. Spray 111, 112 18012 Q6 C 2 3 x x 5 Nl-ST-Q6 O Raw Water 121, 122 m (8
Liq. Poison NP 02A 18019 B M7 x x x x x Nl-ST-M1 X O
NP 02B CRD Pumps ll, 12 18016 B Q6$ 7 2 3 x x x Nl-ST-Q2 Diesel Cooling 102, 103 18026 C x x Nl-ST-MO
. Raw Water O po 1 Constant speed drive, test at nominal nameplate speed.
m 2 Constant Pi assumed, water level recorded for reference.
3 Fixed resistance system, flow to be measured only. 0 Z p
Fixed resistance system, discharge pressure to be measured only.
5 Submerged pump, bearing temperature not measureable.
6 Exception to monthly, quarterly considered adequate in view of past pump surveillance testing performance..
7 Bearing temperatures measured once a year.
8 Constant P; assumed, as the two pumps are run simultanously in series-
I DOCUHENT NO. 81AO/3 Cor d Relief o. 18002 PAGE A 6 37 0
JJ 4l I/I JJ Vaiye 4l Va1ve I/I c O Remarks
/I 0 4l 4l Ho.. I 0
- L Category 0 QC O
JJ L 4l L 4l 'O O 0 N l/l 0 0
8 C D )/4 0 4l 4l N7A 6 R SA.- SRT Setpoint = 1218 psig + 1%
N78 SA C SRT Setpoint = 1227 psig + 1%
N7C 6 R SA C SRT Setpoint = 1236 psig + 196 N7D SA C SRT Setpoint = '1227 psig + 1%
SA SRT Setpoint =. 1236 psig + 1%
N7F 6 R SA C SRT Setpoint = 1218 psig + 1%
Q
%NO N7G 6 R SA C SRT Setpoint = 1227 psig + 1%
R SA C SRT Setpoint = 1205 psig + 1%
f N7H 6
D l
~ N73 6 R SA SRT Setpoint = 1218 psig + 196 I
$ N7K 6 R SA C SRT Setpoint = 1236 psig + 1%
N7M 6 R SA SRT Setpoint = 1218 psig + 196
DOCUHENT NO. 81A0416 "j Core d Relief o. 18002 PAGE A 7 37 C
0 4l IA D Valve 4l Valve UI C 0'l Remarks Ig I 0
- No.. C Category 0 IC O
L 4I Ig Ig I 4l D E 0 N 4J I 0
LJ B III )
Ig U 0 Vl Cr 4l 4l IL N7N SA C SRT Setpoint = 1205 psig + 1%
N7U SA C SRT Setpoint = 1250 psig + 1%
N7R SA C SRT Setpoint = 1250 psig + 1%
SA '
SRT Setpoint = 1205 psig + 1%
SA C SRT Setpoint =.'1250 psig + 1%
D m
DOCUMENT NO. 81A04 Fe er PAGE A 8 5'7
- o. 18005 A
0 4J I/I IO Valve Va1ve III 0 Remarks
- Ho,'. IO A Category I 0
IA o A Cl III I III D E 0 N A 0 0
8 C D Ijl )lO 0 0 III Ol Q 31-03 18 G MO-AC Non-safety related 31-00 18 G MO-AC Non-saf ety related 31-01 18 SC SA 0 ET 31.-02 18 SC SA 0 ET 1) 0 Vl
DOCUMENT NO. 81A Ma P o. 18002 PAGE 0
4J IA 4l Va)ve 4l Va I ve Vl C Remarks 4l O
C L 0 4l
- Ho.'-. C Category 0 CL, E 4l I
I 0 4l ID I- 4l 'D E 0 N L I/I 0 0 4) U 0 4l 4l LJ 8 C D V) OC 01-07 6 G M L 01-08 6 G M L 01-09 6 G M L 01-10 6 G M L 01-11 6 G M L 01-12 6 G M 01-01 20 G MO A 0 LRT,ET 00 Stroke time = 10 sec, Leak limit = 12.9 scfh PIT Q 22 psig c~ 01-02 20 G MO-A LRT,ET 00 Stroke time = 10 sec, Leak limit = 12.9 scfh PIT Q 22 psig
~ 01-03 20 G AO .LRT,ET 00 Stroke time = 10 sec, Leak limit = 12.9 scfh nC PIT Q 22 psig:
3 01-00 20 G AO LRT,ET 00 Stroke time = 10 sec, Leak limit = 12.9 scfh PIT Q 22 psig
k DOCUMENT NO. 01A PAGE A 10 37.
- o. 18002 C
0 IA 4l 4l O 4l Vl Valve Va 1 ve O 0 C 4l O
4l No, ID C L. 0 E
- . C Category 0 4l OC I
O 4l IO I- 4l O E P O Remarks'R-108A 0 N I N O 0
LJ 8 C- D Ijl )II 0 0 4l 4l cK B X X EM C SRT, ET 05 NR-108B B X X 'EM C SRT, ET 05 NR-108C B X X EM C SRT, ET 05 NR-108D B X X 6 R EM C SRT, ET 05 NR-108E B 'X X 6 R EM C SRC, ET 05 NR-108F B X X 6 R EM C SRT, ET i
%50 z 30-02 2
2 G
SC MO-AC C ET ET 05'0-01 08 03 LRT as per'App. 3 LRT as per App. 3
~ 66-07 10 R SA' SRT Added Spring '8l Outage n
66-08 10 R SA C SRT Added Spring '81 Outage fi 66-09 10 R SA C SRT Added Spring '81 Outage
DQCUHENT NQ 81A04 PAGE A 11 37 P . 18002 C
0 I/I I/l 4l 6
Va 1 vs Valve O Vl 0
C Remarks ill
- Ho'. IQ 6 Category C I 0
0 6 Ol O
I-Ol 60 1
0 E N 4J I Iil 0
LJ A 8 61) )c4 0 K
0 0'l 4l CC 66-10 10 R SA C SRT Added Spring 1981 Outage 66-11 10 R SA. C SRT Added Spring 1981 Outage.
66-12 10 R SA C SRT Added Spring 1981 Outage 66-13 10 SA C SRT Added Spring 1981 Outage 66-10 10 R SA C SRT Added Spring 1981 Outage 66-15 10 R SA C SRT Added Spring 1981 Outage 66-16 10 R SA C SRT Added Spring 1981 Outage 66-l7 10 R SA C SRT Added Spring 1981 Outage In Z
~ 66-18 10 R -SA C SRT Added Spring 1981 Outage f
DOCUMENT NO. 8lA04l6 PAGE A 12 P o. 18009 Vl Va1ve Cl Va 1 ve Remarks lg Q
- Ho.- . C Category 0 5 L
4)
I-0 N 4J 0
A B )CO U I/l O lO dl nC 33-02 MO-AC 0 ET, PIT Stroke time = 18 sec.
'T LRT as per App. 3.
33-00 X MO-AC 0 Stroke time = 18 sec.
LRT as per App. 3.
33-01 MO-AC 0 ET, PIT Stroke time = 18 sec.
LRT as per App. 3..
33-03 SC SA 0 ET LRT as per App. 3.
D D
n S
n
C DDDDNENT NO. E1A0416 Dry d Torus PRI 18006 PAGE A 13 37 0
4ll 443 D
Valve 4l)
Valve Vl 0
G U'll Remarks 4ll
- Ho.. ID C Category 43 5
OC 0 ED E
0 L Ul O 0 0 4ll Cl EJ B C D 201.2-25 G M C ET LRT as per App. 3.
Stroke Time = 60 sec 201.2-26 G M C ET LRT as per App. 3.
Stroke Time = 60 sec 201.2-27 G M C ET LRT as per App. 3.
Stroke Time = 60 sec 201.2-28 G M C ET LRT as per App. 3.
Stroke Time = 60 sec 201.2-29 C ET LRT as pe) App. 3.
Stroke Time = 60 sec 201.2-30 G M C ET LRT as per..App. 3.
Stroke Time = 60 sec
~
RQo 20!.2-23 C ET LRT as per App. 3.
Stroke Time 60 s'ec
~ 201.2-20 Yi G M C ET LRT as per App. 3.
Stroke Time = 60 sec 83.1-09 0 G MO AC 0 ET LRT as per App. 3.
Stroke Time = 60 sec R 83.1-10 0 G AO 0 ET LRT as per App. 3.
Stroke Time = 60 sec
- 83. l - l l 0 G MO-AC I RT as per App. 3.
Stroke Time = 60 sec
DOOONENE NO. 81AOA1',iAGE lid Tor Us A 14 37 Dry Pd(I 18006 c
0 02 N
- o. EJ Valve 4l Val ve I- Ih C Remarks 0 11)
- Ho.. 111 C Category E 0
0 5
Q Ol D 0
0 CJ N
V) 4J U
Ul O f-Ol I EE 83.1-12. G AO 0 ET LRT as per App. 3.
Stroke Time = 60 sec 201-07 20 ,G MO AC 0 ET 10 LRT as per App- 3.
201-08 20 G AO 0 ET 10 LRT as per App. 3.
201-09 G MOA 0 ET 10 LRT as per App. 3.
201-10 G AO 0 ET 10. LRT as pet App. 3.
201-16 20 G AO 0 ET 10 LRT as per App. 3.
201-17 20 MO-A 0 ET 10 LRT as per App. 3.
5 201-31 G MOA 0 ET 10 LRT as per App. 3.
~g 201-32. G MOA 0 10 LRT as per App. 3.
D
>s 201 2 32 G MO-D 0 ET 10 LRT as per App. 3.
~,J e
DOCUMENT NO. Sl d Torus PRI PAGE A 15 37 Dry 18006 C
0 Va 1 ve Va 1 ve Vl 0 Remarks fo
- Ho.. C Category L, 0
62 O Ol ill l Ol D E 0 N 4J
)
S 0 IO 0 0 ED A B C Vl 201.2-03 MO-DC 0 ET 10 LRT as per App. 3.
201.2-06 MO-DC 0 ET 10 LRT as per App. 3.
MO-DC 0 ET 10 LRT as per App. 3.
'01.2-33 201.2-39 SC SA 0 ET 16 LRT as per'pp. 3.
201.2-00 SC SA 0 16 LRT as per App. 3.
201.2-67 3/0 SC SA 0 ET 16 LRT as per,App. 3.
+ 201.2-6S 3/0 SC SA 0 ET 16 LRT as per App. 3.
p 201.2-70 3/0 SC SA ET 16 LRT as per App. 3.
~ 201.2-71 3/0 SC SA 0 ET 16 LRT as per App. j.
Pi I>> 68-01 30 SC AO 0 ET 68-02 30 SC AO 0 ET
DOCUMENT NO. Bl Dryw d Torus Pdcl 18006 PAGE A 16 37 C
0 Q. 4J Vl Valve Ol IJ Va l ve I- Ih Remarks t
0 Ho.. (D n
- C Category 0 5 0 Cl ID l- E 4J 0 l 0 0 0 I-8 Ig Cl LJ A B C O aC 68-03 30 SC AO 0 ET 68-00 30 SC AO 0 ET 68-05 AO 0 ET'RT 30 SC ET as per App. 3 68-06 30 SC AO 0 LRT as per App. 3 68-07 30 SC AO 0 ET LRT as pej App. 3 68-08 30 G AO 0 ET 13 LRT as per, App. 3 Stroke time = 5 sec.
0 LRT as per App.
~ 68-09 30 G AO ET 13 3 Stroke time = 5 sec.
'c 68-10 30 AO 0 ET 13 LRT as per App. 3 Stroke time = 5 sec.
D D
n D
DOCUMENT NO. 8 '., 6 Dryw d Torus PAGE A 37 PRI 18010 C
0 IA 4J III Cl Valve Ci Valve 0 VI 0
G Remarks
- No.'. CI C Category C I 0
0 5
0 I-0 Cl N
Cl I P 0
C D Vl )
Ig 0 0 III 0'l i- cCCl 201.7-01 D 1 G AO ET .Stroke time = 60 sec.
LRT as per App. 3 201.7-02 1 G AO ET Stroke time = 60 sec.
LRT as per App. 3 201.7-03 1 G AO ET Stroke time = 60 sec.
LRT as per App. 3 201.7-00 D 1 G AO ET Stroke time = 60 sec.
LRT as per, App. 3 201.7-08 D 1 G AO ET 13 Stroke time = 5 sec.
LRT as pe'r App. 3 201.7-09 1 G AO ET 13 Stroke time = 5 sec.
LRT as per App. 3 201.7-10 D 1 G AO ET 13 Stroke time = 5 sec.
LRT as per App. 3
~ 201.7-11 AO ET 13 Stroke time = 5 sec.
LRT as per App. 3
< 201.2-109 D 3/ii G AO Stroke time = 60 sec.
LRT as per, App. 3 201.2-110 D 3/0 G AO Stroke time = 60 sec.
LRT as per App. 3 f
DOCUMENT NOe SlA043 Drywe d Torus PdcID 13010 PAGE A ls OF 0
4J Vl D Valve Ol Valve O Remarks I-0 4)
Ho.. tO 0
- C t:ategory 0 OC o Ol ID tg L. E 0 N 4J L 0 ID O 0 EA O 201.2-111 D 3/0 G 'AO 0 ET Stroke time = 60 sec.
LRT as per App. 3 201.2-112 D G AO 0 ET Stroke time = 60 sec.
LRT as per App. 3
?
C D
m
?
D n
r DOCUMENT NO. 81AO ~,"'.
Shu PR . 18018 PAGE A 19 37 C
0 Ih 4l Vl Remarks Valve 4J Va l ve 0
- No.. fO 0 C Category L 0
o 4)
ID D E 0 N 4J L 0
EJ Eh )
lg O 0 38-01 10 G MO-AC C ET, PIT - 15 LRT as per App. 3 38-02 MO-DC C ET 15 LRT as per App. 3 38-13 X IO G MO-AC C ET, PIT 15 LRT as per App. j 38-12 10 'SC SA C ET 15 LRT as per App. 3
DOCUMENT NO. 8 PAGE' 2 OF 37 y Cooling . 18017 C
0 4J N Q D Valve 4)
Va l ve IA C 0 Remarks lg O
I 0 S 0 CL C
- Ho, . C Category 0 CC o Ol L. D E P 0 L N Ct 0
A B )
C U 0 4J 4J OC 39-09 MO-AC 0 ET LRT as per App. 3 Stroke time = 38 sec.
39-10 MO-AC 0 ET LRT as'per App. 3 Stroke time = 38 sec.
39-07 MO-DC 0 ET LRT as per App. 3 Stroke time = 38 sec.
39-08 MO-DC 0 ET LRT as per, App. 3 Stroke time = 38 sec.
39-05 AO C ET, FST LRT as per App. 3 Stroke time = 60 sec.
I 39-06 AO C ET, FST LRT as per App. 3 Stroke time = 60 sec.
60-17 AD C ET Stroke time = 10 sec.
4
%50
~ 60-18 AD C ET Stroke time = 10 sec.
P 39-01 '
E M g~
39-02 Z
r DOCOHENT NO. 81A0416 Em y Cooling PAGE A 21 0 C
0 III III III III Remarks Valve Val ve O 0 C
Q III C
- Ho.'. C Category I 0
C4 5
'o III III III I E 0 4J I-0 EJ A B C )
III U 0 lh Ct Ol 4)
OC 39-03 10 SC SA C ET 17 Exercised during system testing 39-00 B 10 SC SA C ET 17 Exercised during system testing 60-11 L 60-12 4 G 39-11 B AD ET, FST 13 LRT as per App. 3 Stroke time = 5 sec.
39-12 1 G AD ET, FST 13 LRT as per App. 3 Stroke time = 5 sec.
39-13 I G AD ET, FST 13 LRT as per App. 3 Stroke time = 5 sec.
g 39-10 AD ET, FST 13 LRT as per App. 3 Stroke time = 5 sec.
g 60.1-10 L a
60.1-15 3
DOCUMENT NO 81A041 PAGE A 22 7 Eme y Cooling Pdc . 18017 lh 6 Valve lO Va I ve O CL C O Remarks 4)
- No.'.
IQ C
o Category C I OC 4l I 0 0 N l/l Q' 0 IO 4)
A B O 60.1-16 60.1-17 G M L 05-01 G AO ET 13 LRT as per App. 3 Stroke time = 5 sec.
05-02 G AO 13 LRT as per App. 3 Stroke time = 5 sec.
05-03 G AO ET 13 LRT as per App- 3 Stroke time = 5 sec.
05-00 G AO ET 13 LRT as per App. 3 Stroke time = 5 sec.
. DOCUMENT NO. 81AI.-'..
PAGE A P d7 Liq ison . 18019 C
0 IA 4l Valve 4J Va 1 ve Ol C Remarks 4I O
C I 0
II 4I
- l3o.'. C Category 0 E 4I I II-0 4I III Ig 4l I D E P 0 4J I I/l 0 0
)
IO 0 0 f-Ol oC4I 45 OC
~
01-06 x 2.5 G M LC 01-12 x 1 G M LC 01-13 M LC 01-18 2.5 G M LC 02-01 2.5 M L 02-02 2.5 G M L NP05 A 15 E. XT Ii NP05-0 1Yi E XT I
D
'9 NP00-A SA. C SRT Setpoint = 1000 psig NPOO-,B SA C SRT Setpoint,= 1000 psig
DOCUMENT NO. 81 PAGE A 24 37 Liq ison PR . 18019 C
0 I/I I/l II)
Valve III Va 1 ve Ih C Remarks 4J O c 0
- Ho.'. III 6-C Category 5
'a III I- III E D 0 N I 0 IQ 0 Ol 0 LJ A B C O I2C 02.1-02 15 SC SA 0 ET Ol LRT as per App. 3 02.1-03 1Yi SC SA 0 ET Ol LRT as per App. 3 x 2Yi G LO 02-03 x15 G LO 02-00 1Yi G LO 02-13 1Yi G L 1 Yi G LO 2Yi G LO 25 G'O 1Yi G LO
Dm:UMENT NO.~81,!:.: 6 PAGE A .: F 37 Liq iso n P o. 18019 C
0 4J Ho.I.'/l Valve 4l IO C
Valve Category 4l 0
C L 0
0 II Ul 0
C 4l S.
I Remarks D 4l IO IO I 4l D E 0 N 4J I 0
8 C D )
IO V K
0 IA O 4l 4I 02-18 M L 02.1-01 M L 02-19 SC SA ET Exercised during Pump Testing 02-20 SC SA ET Exercised during Pump Testing D
D n
VI
DOCUMENT NO ' 16 Co ay . 18007 PAGE A OF 37 0
4)
Valve 4l Valve 4) IA Remarks O LL 0
- Ho.'.
lD C I CL C Category I- 0 o 4l ID L D E 0 N L 0 Q V 0 C D Vl 81-01 MO-A ET -Stroke time = 90 sec.
81-02 MO-A ET Stroke time = 90 sec.
81-21 MO-A ET Stroke time = 90 sec.
81-22 G MO-A ET Stroke time = 90 sec.
81-07 12 SC SA ET Simultaneous with pump testing (3'000 gpm) 81-08 12 S SA ET Simultaneous with pump testing (3000 gpm) 81-27 12 SA ET Simultaneous with pump testing (3000 gpm)
Z 81-28 12 SA ET Simultaneous with pump testing (3000 gpm)
~
81-73 3/ SA SRT Setpoint = 85 psig 81-70 3/ R SA SRT Setpoint = 85 psig
0 DOCUMENT NO.. '.
416 Cor y P . 18007 PAGE OF 37 Vl I/l 4l Valve Valve C 4l Remarks
- Ho.. /tl I E C Category 0 4l O
4J I 4-4l /g 4l l E 0 l 0
EJ c nF. )
/tl U 0 I/l O 4l 4l CC 4l CC 81-75 3/0 R SA C SRT Setpoint = 85 psig 81-76 3/0 R SA C SRT Setpoint = 85 psig 81-11 12 R SA C SRT Setpoint = 320 psig 81-31 12 R SA C SRT Setpoint =.320 psig 81-77 3/0 R SA C SRT Setpoint .'60 psig I
81-78 3/4 R SA C SRT Setpoint = '60 psig 31-79 3/0 R SA SRT Setpoint = 60 psig WOO c 81-80 3/0 R SA SRT Setpoint = 60 psig gn 81-09 12 G P3 81-10 12 G M n
DOCUMENT NQ. 81AO Cor PR . 18007 PAGE A 28 37 c
0 I/l Ill Ill 4J Q IIl C Remarks Valve Valve U 0 Q O
lll Ho.. Io C I Il E
~
C Category 0 Q 0 lg III I D E P 0 4J l IIl 0 0 O 0 4)
LJ A 8 OC 81-29 x 12 G M LO 81-30 x 12 G M LO 58.1-01 G MO C ET LRT as per App. 3 00-03 12 SC SA 0 ET Simultaneous with pump testing (3000 gpm) 00-13 12 SC SA 0 ET Simultaneous with pump testing (3V00 gpm) 00-05 G MO-AC C ET Stroke time = 25 sec.
00-06 G MO AC C ET Stroke time = 25 sec.
z 93-51 12 .G MO-AC C ET Stroke time = 70 sec.
P
~ 93-52 12 G MO-AC C ET Stroke time = 70 sec.
s00 02 12 G MO-AC 0 ET Stroke time = 25 sec.
DOCVMENT NO. 8 ~ i 6 Cor P* . 18007 PAGE OF 37 c
0 Ho,.'l CL Ol 4J 44 D Valve 4)
Valve I- Vl C 0 Remarks O
l 0 Q 4)
ID C n 6
- C Category 0 Q I
0 l-0 4l N
Ol I P D N 0 0
LJ 8 C Vl )
l0 U 0 8 Q n
00-12 12 G MO-AC 0 ET Stroke time = 25 sec.
00-01 12 G MO-AC C ET, PIT Stroke time = 25 sec.
00-09 12 G MO-AC C ET, PIT Stroke time = 25 sec.
00-10 12 G MO-AC C ET, PIT Stroke time = 25 sec:
00-11 12 G MO-AC C ET, PIT Stroke time = 25 sec.
l4 DOCUMENT NO..:'. 416 Con ent Spray and Raw Nater PR . 18012 PAGE OP 37 L
0 Vl I/l 4l 6
Valve Valve U IA 0 C Remarks lg Q No.. C I Q
- Category I- ~ 0 E Ol I
o l- Cl, ID 0 N Cl E L 3 0
0 EJ C D tlat ) U 0 Ul Cl tll 93-09 X 12 SC SA 0 ET Exercised during Pump Testing 93-10 12 SC SA 0 ET Exercised during Pump Testing 93-11 C 12 SC SA 0 ET Exercised during Pump Testing 93-12 12 SC SA 0 ET Exercised during Pump Testing 93-13 12 G M 93-10 12 G M
~ 93-15 12 j 93-16 12 Z
> 93-17 12. G M 8
93-18 12 G M
DOCUMENT NO. ~ ','16 Con ent Spray and Raw Water . 18012 PAGE A F 37 c
0 4J Vl ill Remarks Valve Valve Vl 0
Ho.. ID L 0
- C Category 0 O lD l D 0
0 LJ A B C 'lN 4J 0 0 93-19 x 12 G 93-20 x 12 G 93-21 93-22 93-23 93-20
~
WSO 93-26 12 G MO-AC 0 ET Stroke time = 70 sec.
cp 93-27 12 G MO-AC 0 ET Stroke time = 70 sec.
9 93-28 12 G MO-AC 0 ET Stroke time = 70 sec..
" 93-09 12 G MO-AC C ET Stroke time = 70 sec.
LRT as per App.3 93-50 12 G MO-AC C ET Stroke time = 70 sec.
LRT as per App. 3
DCCUNENT NO. (4" 416 Con nt Spray and Raw Water P*l 18012 PAGE A OP 37 C
0 4J Vl Cl Valve IU Va l ve I-. Vl G Remarks O 0 ill
- l)0.. IQ C Category C E 0
0 I
l-o Ol I
0 4J l P
Ih 0
LJ A 8 )
Q U 0 0 0'J 93-25 12 Vl0-AC 0 ET Stroke time = 70 sec.
80-17 12 SC ET 02 80-37 12 SC SA 0 ET 02 80-18 12 SC SA 0 ET 02 80-38 12 SC SA 0 ET 02 80-19 r
SC SA 0 ET 02 80-39 X 3 SC ET 02
,PO-66 SC SA ET 02 r 80-68 3 SC SA 0 ET 02 D
n
)80-06 '12 SC SA 0 ET Exercise during Pump Testing Z
80-26 12 SC SA 0 ET Exercise during Pump Testing
~
ri~
"'16 DOCUNENT NO.
~ Con nt Spray and Raw Water PR . 18012 PAGE A OF 37 C
0 673 8 Vl C Remarks Va) ve Va 1 ve. 0 Q
- .Ho.. IQ L 0 c Category 0 5 I
O Cl f0 6l3 3 O) D E D 0 N 43 L.
0'J B C D 613 )lO V 0 613 4l Cl Ct EE 80-05 12 SC SA ET Exercise during Pump Testing 3
80-25 12 SC SA 0 ET Exercise during Pump Testing 80-08 x 12 M LO 80-28 x 12 M LO 80-07 x 12 M LO 80-27 12 M L
~
%80 60-67 SC SA 0 ET 02 6 SO-65 '3 SC SA 0 ET 02 n
80-15 12 AO 0 ET Stroke time = 60 sec.
f 80-16 12 AO 0 ET Stroke time = 60 sec.
DOCUMENT NO e Sl I .i'6 r Con nt Spray and Raw Water Pdr. 18012 PAGE QF 37 0
4J tO Ul D Valve 4l Valve I- Vl C O Remarks 0 I) 4)
- Ho.'. ID L. 0 C Category 0 5 OC L
a Ol D
0 ~
0 B C D )
Q 0 IA Ct I- 056 4l 80-35 12 G AO 0 ET Stroke time = 60 sec.
80-36 12 G AO 0 ET Stroke time = 60 sec.
I 80-00 6 G C ET 10 Valves to be added to App. 3 Testing 80-01 6 G AO C ET 10 Valves to be added to App. 3 Testing 80-03 6 G M -C ET 10 Valves to b'e added to App. 3 Testing 80-00 6 G AO C ET 10 Valves to be added to App. 3 Testing 80-05 6 G AO C ET 10 Valves to be added to App. 3 Testing g 80-01 12 G MO-AC 0 ET Stroke time = 70 sec.
~ 80-02 12 G MO-AC 0 ET Stroke time = 70 sec.
i 80-21 12 G MO-AC 0 ET Stroke time = 70 sec.
'80-22 12 G MO-A Stroke time = 70 sec.
Class Coordinates e +
tti 0
C Size (inches)
Va l ve Type Actuator Type Normal Position Test Requirements OO CO h0 ~
Relief Requests
DOCOMENT N '.'."."- 04l6'-
Dies erator Raw Water pa . 18026 PAG 6 OP 37 C
0 4l Valve Cl Va l ve 0 I/I C Remarks Ig c 0 No.. I 0 6 C Category 0 Cl I
0 C) IQ I D E D 0 N 4J I Vl 0 0 Cg V 0 4l Q EJ A 8 l/l w) 72-66 C SC SA 0 ET Exercised during D/G Testing 72-67 0 SC SA 0 ET Exercised during D/G Testing 72-68 0 SC SA 0 ET Exercised during D/G Testing 72-69 SC SA 0 ET Exercised during D/G Testing II Il n
ill M
I,
) DOCUMENT "" OlA04'16 CR aulics Pdt . 18016 A 37 OF 37-C 0
IA Valve 6 Vl C Remarks Ig
.Valve 0 Ol Ho.. 0
- C Category 0 5 D 4)
I D 0 4J Vl Q 0 lg U LJ A B O f-4l CCCl 00.2-15 G AO 0 ET Stroke Time = 60 sec 00.2-16 AO 0 ET Stroke Time = 60 sec 00.2-17 G AO 0 ET. Stroke Time = 60 sec 00.2-18 AO 0 ET .Stroke Time = 60 sec CV-126 3/0 AO C ET 07 CV-127 3/0 AO C ET 07 SC SA 0 07 C
p n
f
1 DOCUMENT NO, PAGE OF NUCLEAR ENERGY SERViCES, INC.
APPENDIX B VALVE:RELIEF'EQUESTS FORiVI = iNES 205 2/80
C DOCUMENT NO.
p>gE B 1 OF 10 NUCLEAR ENERGY SERVICES, INC.
VALVERELIEF REQUESTS Appendix B contains relief requests for valves so indicated in Appendix A. The detailed information is presented in standard forms to document that the burden in complying with the code requirements is not justified by the increased level of safety obtained from the testing.
The majority of the relief requests are for the excerising of nontestable swing check valves in Nine Mile Point Unit 1. These valves do not have the necessary instrumentation needed to comply with code requirements. In some cases, however, the adequate closing of the valve will be demonstrated during the inservice testing of an associated pump.
Full-stroke valve cycling in the Main Steam system during nominal power level operations could subject the plant to undesirable operating conditions, such as high pressure and/or high flux scram. A drop-to 0096 power is proposed to enable testing without a scram. Such a reduction in. power occurs several times per year (i.e., during rod swapping, etc.) and provides an opportunity for the'test.
Category A leak valve testing will be conducted in accordance with Appendix 3 to 10 CFR 50, except those exemptions requested from that appendix (see Attachment A to letter from G.K. Rhode "Request for Exemption" dated March 3, 1977). Appendix 3 is recognized by the NRC as the governing regulation for containment leak rate testing.
Since all Category A valves are containment isolation valves and are tested under Appendix 3, we believe a duplicate leak rate testing program for ASME Section XI Pumps and Valves would not be justified.
FORM 0 NES 205 2/80
. P DOCUMENT NO.
NUCLEAR ENERGY SERVICES, INC.
AGE B 2 pF'0 RELIEF REQUEST BASIS 01 Valve ID Function P R ID 02.1-02 Prevent back leakage from reactor 18019 02.1-03 vessel to the liquid poison system.
'est Requirement: Full stroke exercising of the valve quarterly.
Basis for Relief: This valve does not have an attached position indicating device (local or remote), nor does the system have adequate sensing devices to give secondary indications of the valve position.
Alternate Testing: During every refueling outage the liquid poison system is tested. These valves will be exercised during, this test.
RELIEF REQUEST BASIS 02 Valve ID Function P R ID 80-17 To prevent back flow from Drywell spargers 18012 80-18 to the balance of the system when redundant 80-37 loop is operating.
80-38 80-19 To prevent back flow from the Torus 18012 80-65 80-66 80-67 80-68 80-39 Test Requirement: FWl stroke exercising of valve quarterly.
Basis for Relief: These valves do not have an attached position indicating device Qocal or remote), nor does the system have adequate: sensing, devices to give secondary indications of the valve position.
Testing wo Wd require pressurization of the drywell, necessitating shutdown quarterly.
Alternate Testing: During the Appendix, 3 type A test, which is conducted every refueling outage, the valve is stroked to the open position.
FORM 0 NES 205 2/80
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE ~GF~
RELIEF REQUEST BASIS 03 Function P R ID Valve ID 30-02 To prevent back flow. from the reactor 18002 vessel into the head spray system.
Test Requirement: FWl stroke exercising of the valve quarterly.
Basis for Relief: This valve does not have an attached position indicating device (local or remote), nor does the system have adequate sensing devices to give secondary indications of the valve position. The valve passively fulfills its safety function.
Alternate Testing: This valve is leak rate tested under Appendix 3 every refueling outage.
RELIEF REQUEST BASIS 00 Valve ID FunctIan PAID Main Steam Blocking Valve 18002 01-00 01-03 01-02 01-01 Test Requirement: Full stroke exercising and stroke time verification quarterly.
Basis for Relief: Full-stroke testing at full power would cause a scram on high pressure and subject the plant to undue thermal cycling stress.
Reduction in power to 00% should limit the adverse effects of testing.
Alternate Testing: During rod swapping and other times when power is reduced to the 0096 level, testing shall commence (not to exceed once per quarter). Full stroke testing and stroke time verification will be performed during each refueling outage.
FORM 0 NES 205 2/80
DOCUMENT NO. 8M0416 AGE B 4 pF 10 RELIEF REQUEST BASIS 05 Valve ID Function P 2 ID NR-108-A thru F Electromatic relief valves 18002 Test Requirement: Full relief test exercising of valves quarterly.
Basis for Relief: 'ull L stroke testing of the electromatics on a quarterly basis would cause undue thermal stresses on the suppression chamber.
Alternate Testing: These valves are tested at the beginning of every refueling outage.
RELIEF REQUEST BASIS 06 Valve ID Function PAID 31-01 To prevent back flow into the feedwater system 18005 31-02 from the reactor. L Test Requirement: Full stroke exercising quarterly.
Basis for Relief: These valves do not have an attached position indicating device Oocal or remote), nor does the system have adequate sensing devices to give secondary indications of the valve position.
Alternate Testing: The valves shall be integrated leak rate tested every refueling outage.
¹ FORM NES 205 2/80
DOCUMENT'NO PAGE B 5 OI=
NUCLEAR ENERGY SERVICES. INC.
RELIEF REQUEST BASIS 07 Valve ID Function P 2 ID CV 126 Low sid scram control valve. 18016 CV 127 High side scram control valve.
'138 water header check valve.'ooling Test Requirement: Full stroke exercising testing quarterly.
Basis for Relief: Exercising these valves quarterly would:
- 1. Increase wear on the control rod drive seals due to isolation of cooling water.
- 2. Cause undue termal shock.
- 3. Cause fuel damage due to flux peaks.
Alternate Testing: Following each refueling outage all control rods are following each scram from rated pressure, the mean scram-'ested, 90% insertion time for at least 8 control. rods is determined and after each outage not initiated by a scram, eight rods're scram tested, results of the above listed test verifies proper operation of these valves.
RELIEF REQUEST BASIS 08 Valve ID Function P 2 iD 30-01 Head Spray outside isolation valve 18002 Test Requirement: Full stroke'xercising test and stroke-time verification quarterly.
Basis for Relief: This valve is a normally closed passive component not required to change its position to fulfillits safety function.
Alternate Testing: The valve shall be integrated leak-tested every refueling outage.
FORMCNES 205 2/80
DOCUMENT NO 81A0416 L PAGE j! E OF NUCLEAR ENERGY SERVICES, INC.
RELIEF REQUEST BASIS 09 Valve ID Function PE! ID ill, 112 Core spray injection pumps 18007 121, 122 I ill, 112 Core spray topping pumps 18007 121, 122 ill, 112 Containment spray pumps 18012 121, 122 CRD 11, 12 Control rod drive pumps 18016 ill, 112 Containment spray raw water pumps 18012 121, 122 Test Requirement: Monthly test.
Basis for Relief: The past record at NMP-1 indicates the reliability of the pumps, which would not improve by monthly cycling, which would promote excess stress and strain on pump/motor design life.
Alternate Testing: Testing will be scheduled quarterly.
RELIEF. REQUEST BASIS 10 Valve ID Function PE! ID 80-00 Containment spray and raw water system 18012 80-01 gate valve..
80-03 80-00 80-V5 201-07, 08, Drywell and torus gate valves 18010 09~ 10~ 1 6~ 1 7~
31, 32 201.2-32, 03, 06, Drywell and torus gate valves. 18006, 33 18010 Test Requirement: Exercising of the valve from its normal position.
Basis for Relief: This valve is not required to, change its position to fulfill its safety function due to its passive nature.
Alternate Testing: Verify and record valve position before and after each valve operation when the environment permits. In addition, these valves are leak tested per Appendix 3.
FORM ONES 205 2/80
0 DOCVMENT NO.
PAGE B 7 OF NUCLEAR ENERGY SERVICES, INC.
RELIEF REQUEST BASIS ll Valve ID Function P dcID 33-03 Prevent backflow from reactor feedwater 18009 header into reactor cleanup system.
Test Requirement: Full stroke exercising quarterly.
Basis for Relief: This valve does not have an attached position indicating device (local or remote) nor does the system have adequate sensing devices to give secondary indication of the valve position.
Alternate testing: The valve is included in the Appendix 3 type A leak test which is performed every refueling outage.
RELIEF REQUEST BASIS 12 Valve ID Function P 2 ID 39-06 Emergency cooling outside isolation valve l.80l7 39-05 Test Requirement: Full store exercising and stroke time verification quarterly.
Basis for Relief: Full-stroke testing at power or stand by conditions would subject the plant to undue thermal cycling stress.
Alternate Testing: Full stroke testing and stroke time verification will be performed during each cold shutdown (not to exceed once per quarter).
FORM SNES205 2/80
t A DOCUMENT NO, 81A0416 PAGE ~E PF 10 NUCLEAR ENERGY SERVICES, INC.
RELIEF REQUEST BASIS 13 Function P R ID Valve ID
'5-01, 02, 03, 00 Containment isolation 18017 9-11, 12, 13; 10 18017 68-08, 09, 10 18006 201.7-08, 09, 10, ll 18010 Test Requirement: Conduct trend analysis of stroke times.
Basis for Relief: Trend analysis of fast acting valves is inconclusive of valve operation due to the speed at which these valves operate.
Alternate Testing: Corrective action will'e taken if the stroke time exceeds 5 seconds.
RELIEF REQUEST BASIS 10 r
Valve ID Function P R ID 58.1-01 Core spray torus makeup isolation valve 18007 Test Requirement: Full stroke exercising test and stroke-time verification quarterly.
Basis for Relief: This valve is a normally closed passive component not required to change its position to fulfillits safety function.
Alternate Testing: The valve is included in the Appendix 3 type A leak test which is. performed every refueling outage.
FORM 0 NES 205 2/80
l' ppCUMENT Np 8>>40>6 j
PAGE ~ OF NUCLEAR ENERGY SERVICES, INC.
RELIEF REQUEST BASIS 15 Valve ID Function P k ID 38-01'8-02 Isolate reactor shutdown cooling 18018 system from reactor.
38-12 38-13 Test Requirement: Full stroke exercising and stroke-time verification quarterly.
Basis for Relief: This valve is a normally closed passive component not required to change position to fulfillit safety function.
Alternate testing: These valves are included in the Appendix 3, type A leak test which is performed every refueling outage.
RELIEF REQUEST BASIS 16 Valve ID Function P RID 201.2-39 Prevent backflow into N2 purge-tip system 18014 201.2-00 201.2-67'01.2-68 Prevent backflow into drywell H2-02 18010 Sampling system 201.2-70 Prevent backflow into torus H2-02 18-10 201.2-71 Sampling system Test Requirements: Full stroke exercising quarterly.
Basis for Relief: This valve does not have an attached position indicating device (local or remote), nor does the system have adequate sensing devices to give secondary indication of the valve position.
Testing would require pressurization of the drywell, quarterly.
Alternate Testing: These valves are included in the Appendix 3, type A leak test which is performed every r efueling outage.
FORM 0 NES 205 2/80
r P
DOCUMENT NO 81A4016 A
PAGE ~BO OF 10 NUCLEAR ENERGY SERVICES, INC.
RELIEF REQUEST BASIS 17 Valve ID Function FR ID 39-03 Prevent reverse flow of the emergency 13017 39-00 Cooling system Test Requirement: Exercise test quarterly.'ull-stroke Basis for Relief: exercise testing at power or standby 'conditions would subject the plant to undue termal cycling stress, nor does the valve have an attached position incic'ting device (local or remote).
Alternate Testing: The valve will be full stroked during the hydrostatic test following each refueling outage.
FORM 0 NES 205 2/80
II DOCUMENT NO.
'AGE C1 OF.
'20 NUCLEAR ENERGY SERVICES, INC.
APPENDIX C TEST SCHEDUL'ES FORM -. NES 205 2/80
S DOCUMENT NO, 83%0416 PAGP C2 OF 20 NUCLEAR ENERGY SERVICES, INC.
TEST SCHEDULES The pump inservice testing frequency is the Pump List of Appendix A. Appendix C presents the testing requirements and frequencies for the inservice testing of valves.
These tables are intended to provide scheduling information for Nine Mile Point Unit 1 operating personnel in integrating Section XI Pump and Valve Inservice Testing requireme'nts with Technical Specification surveillance testing programs.
Table C-1 lists all required valve testing grouped by system. Valve ID's, test frequencies, field test procedures and test limits are specified.'able C-2 reorganizes. the same in'formation by frequency and field test procedures.
The schedules presented here are applicable to a 20 month period starting in December; 1979 and. ending in August, 1981. The program will be updated to "applicable Code Addenda for subsequent 20 month intervals..
FORM>>NES 205 2/80
DOCUMENT NO. SlA0416 NUCLEAR ENERGY SERVICES, INC. PAGE OF Valve Test 2
NMPC field NES System 1.D. I Test Limits
/
Freq. test, general Req's. procedure procedure Main Steam 01-01 A LRT Leak=12.9 scfh pslg I 22 N 1-ISP-25.1 81A0411 ET/p 7% part stroke 'Wb N 1-ST-V4 81A0412 ET Stroke time=10 sec C Nl-ST-RS 81A0412 PIT C Nl-ST-RS 81A0413 01-02 A LRT'T/p Leak=12.9 scfh psig I 22 N 1-ISP-25.1 81A0411 7% part stroke Wb Nl-ST-V4 8IA0412 ET'IT Stroke time=10 sec C N 1-ST-RS 81A0412 C Nl-ST-RS 81A0413 01-03' LRT Leak=12'.9 scfh pslg I 22. N 1-ISP-25.1 '1A0411 ET/p . 7% part stroke Wb N 1-ST-V4 81A0412 ET, Stroke time=10 sec C N 1-ST-RS 81A0412 FST 01-04 A .LRT Leak=12.9 scfh psig I 22 N 1-ISP-25.1 81A041-.
ET/p 7% part stro'ke Wb Nl-ST-V4 181A04.
. ET,. Stroke time=10 sec. C Nl-ST-RS 81A0412 FST NR-108 C SRT 'etpoint=1090 psig N 1-ST-C2 81A0415 NR-108 C Setpoint=1090 psig Nl-ST-C2 '1A0415 NR-108 C SRT ~
Setpoint=1095 psig Nl-ST-C2 81A0415 l
NR-108 C SRT Setpoint=1095 psig N 1-ST-C2 81A0415 NR-108 C SRT Setpoint=1100 psig Nl-ST-C2 81A0415 NR-108 C SRT Setpoint=1100 psig Nl-ST-C2 81A0415 l LRT Leak Rate Test C Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Pull-stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Q Quarterly PlT Position indicator Test Bi-weekly FST Fail Safe Test XT Explosive Test Table C-1 FCRM NES 205 2/80
=..
DOCUMENT NO.
PAGE OF NUCLEAR ENERGY SERVICES, INC.
Valve Test lPPC field NES System Z.D. 1 Tes t Limits 2 Freq. test general Req's. procedure procedure Main Steam N?A>> C SRT psig 2C by NMPC 81A0415 N?B SRT 'etpoint=1218 Setpoint=1227 psig 2C by NMPC 81A0015'1A0015.
N7C C SRT Setpoint=1236 psig 2C by NMPC N?D C Setpoint=1227 psig 2C by NMPC 81A0015 SRT'RT'RT Setpoint=1236 psig 2C by NMPC 81A0015 N?F Setpoint=1218 Ps1g 2C by NMPC 81A0415 N7G SRT Setpoint=1227 psig 2C by NMPC 81'A0415 E
N?H C SRT . Setpoint=1205 psig 2C,. by NMPC 81A0015 Setpoint= 1218 psig 2C by NMPC 81A0415 N?K SRT. Setpoint=1236 psig 2C by NMPC 81A0415 N7M C SRT Setpo1nt=121S psig 2C by NMPC 81A0415
'7N SRT Setpoint= 1205 ps1g 2C by NMPC 81A0415 N7U SRT Setpoint=1254 psig 2C by NMPC 81A0015 I
N7R G SRT Setpoint=1254 psig 2C by NMPC 81A0015 N7S, SRT Setpoint=1205 pslg 2C by NMPC 81A0015 N7T SRT Setpoint=1250 psig 2C by NMPC 81A0015
+This test shou d be sche uled y the val e serial no.'s,.not by flan e 'loca ions.
2 LRT Leak, Rate Test C Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Full-stroke Exercise Testing 2C. Once every two cycles SRT Safety Relief Test Q Quarterly PIT Position Indicator Test Wb Bi-weekly FST Fail Safe Test XT Explosive Test Table C-l FORM -.. NES 205 2/80
DOCUMENT NO.
NUCLEAR ENERGY SERVICES, INC. PAGE OF Valve Test 2
NMPC field NES System I.D. 1 Test Limits Freq. test general Req's. procedure procedure Feedwater 31-03 B ET/p 7% part stroke Wb Nl-ST-V4 81A0412 Stroke time=10 sec C N 1-ST-R8 81A0012, ET'IT'T/p C Nl-ST-R8 81A0013 31-00 B 7% part stroke Wb Nl-ST-V0 81A0012 ET Stroke time=10 sec C Nl-ST-R8 81A0012 PIT C. Nl-ST-R8 81A0413 68-01 C by NMPC . 81A0415 l
68-03 C by NMPC 81A0015 .'
~
68-00" C ET by NMPC 81A0015 1 L'eak Rate Test 2, LRT '
Cyclic (everv scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET'RT Full-stroke Exercise Testing 2C Once every ceo cycles Safety Relief Test Q Quarterly PET Position Indicator Test Wb Bi-weekly FST Fail Safe Test XT Explosive Test.
Table C-1 I
FORM NES 205 2/80
DOCUMENT NO SlA0416
' PAGE G6 OF 20
~
NUCLEAR ENERGY SERVlCES, INC.
Valve Test 2
NMPC field NES System I.D. .1 Test Limits Freq. test general Reg's. procedure procedure Reactor '33-01 ET Stroke time=18 sec Q N I-ST-Q0 81A0012 Cleanup . PIT C Nl-ST-Q0 8IA0413, 33-02 ET Stroke time=18 sec Q N I-ST-Q0 '81A0012 PIT C Nl-ST-Qe 81A0013
.33-04 B ET Stroke time=18 sec Nl-ST-Q0 8IA0412 .
72-66 C ET Q by NMPC 81A0015 72-67 C ET Q by NMPC 81A0415 72-68 C ET Q .by NMPC 81A0015 I
72-69 C ET by NMPC 81A0015 1 2' LRT Leak Rate Test Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Full-stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Q Quarterly PIT Position Indicator Test Vb Bi-sleekly FST Fail Safe Test XT Explosive Test Table C-1 FORM"-.. NES 205 2/80
DOCUlvlENT NO Sm0416 PAGE PF 20 NUCLEAR ENERGY SERVICES, INC.
Valve Test 2
NMPC field NES System I.D. 1 Test Limits Freq. test general Req 's. procedure procedure Shutdown 38-01 ET Stroke time=00 sec C Nl-ST-R8 81A0412 Cooling- PIT C Nl-ST-R8 8IA001,3 38-13 A/ ET Stroke time=00 sec C N 1-ST-R8 81A0012 PIT C N 1-ST-R8 8IA0013 38-02 A/ . Stroke time=00 sec Nl-ST-R8 81A0412 ET'38-12 A ET Stroke time=00 sec N 1-ST-R8 . 8IA0012' Leak Rate Test 2 LRT'T/p C Cyclic (every scheduled Part-stroke Exercise Testing refueling outage)
ET Full-stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Q Quarterly PTT Position Indica tor Test Bi-weekly FST. Fail Safe Test XT Explosive Test Table C-1 I
FORM NES 205 2/80
I DOCUMENT NO.,
PAGE CE QF 20 NUCLEAR ENERGY SERVICES, INC.
Valve . Test 2 NMPC field NES System I.D. a 1 Test Limits Freq. test general
- t. Req's. procedure procedure.
Emer gency 39-09 B ET Stroke time=38 sec, Q '1-ST-QO 81A0412 Condenser 39-10 '
Stroke time=38 sec N 1-ST-Q4 81A0012 S1A'0012.
ET'9-07'
~
Stroke tim'e=38 sec N 1-ST-Q0 ET'9-0S B ET. Stroke time=38 sec N 1-ST-QO 81A0412 39-05 B ET, Stroke time=60 sec N 1-ST-Q0 81A0012 FST 39-06 B ET; Stroke time=60 sec C N 1'-ST-QO 81A0012.
FST' 39-11 ET, Stroke time=5 sec Nl-ST-QO 81A0012 FST 39-12 B ET; Stroke time=5 sec N 1-ST-QO 81A0012.
FST 39-13 ET;.. Stroke time=5 sec N 1-ST-Q0 81A0012.
FST 39-10 .
B ET, Stroke time=5 sec N 1-ST-Q0 81A0012 FST Emergency 60-17 B ET No limit on stroke. N 1-ST-M2 Cond. Make time. 81A0012'1A0012 Up 60-18. B. ET No limit on stroke. N 1-ST-M2 time-V
\
1 2 LRT Leak Rate Test C Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Full-stroke Exerci.se Testing 2C Once every two cycles SRT Safety Relief Test Q Quarterly PIT Position Indicator Test Bi-weekly FST Fail Safe Test XT Explosive Test Table C-1 FORM INES 205 2/80
C I I NUCLEAR ENERGY SERVICES. INC.
I DOCUMENT NO.
PAGE ~OF~
Valve Test 2 NMPC field NES System Z.D. 1 Test Limits Freq. test general Req's. procedure procedure Core Spray 81-01 ET Stroke time=90 sec N 1-ST-Q 1 81A00 12 81-02, B ET Stroke time=90 sec N 1-ST-Ql 81A0012.
81-21 B Stroke time=90 sec Nl-ST-Ql 81A0012 81-22 B ET, Stroke time=90 sec N 1-ST-Ql 81A0012 00-05 B Stroke time=25 sec Nl-ST-Ql 81A0012.
00-06 B Stroke time=25 sec. Nl-ST-Ql 81A0012 ET'T I
. Stroke time=25 sec Nl-ST-Ql 81A0012 I
00-02'0-12 Stroke time=25 sec N 1-ST-Ql 81AOV12 00-01 ET Stroke time=25 sec Q Nl-ST-Ql 81A0012 PIT C Nl-ST-Ql' 81A0413 00-09 B ET Stroke time=25 sec N 1-ST-Ql 81A0412, PIT C. N 1-ST-Q 1 81A0013.
00-10 ET Stroke time=25 sec N 1-ST-Ql 81A0012, PIT. Nl-ST-Ql 81A0013 00-11 B ET Stroke time=25 sec Q 1-ST-'Q 1 81A0012.,
PIT C' Nl-ST-Ql 81A0013 93-51 B ET No stroke time Nl-ST-Ql 81A0012 limit 93-52 No stroke time Nl-ST-Ql 81A0412 limit 1 2 LRT Leak. Rate Test C Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Full-stroke Exercise Testing 2C'nce every two cycles SRT Safety Relief Test Q Quarterly PIT Position Indicator Test Wb Bi-weekly FST Fail f Sa e Tes t XT Explosive Test Table C-1 FORM =.. NES 205 2/80
DOCUMENT No 81A0416 PAGE OF Valve C Test 2 NMPC field NES System I.D. a 1 Test Limits Freq. test general t ~ Req's. procedure procedure Core Spray 81-07 ET by NMFC 81A0015 81-08 ET by NMPC 81A0015 81-27 by NMPC 81A0415 81-28 ET by NMPC 81A0415 CV-NC-11 ET Q 81A0412 NC-12 ET Q 81A0012, CV-126 B 127. B 1
Leak.,Rate Test 2 LRT C Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Pull-stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Q Quarterly PIT Position Indicator Test Bi-weekly FST Fail Safe Test XT Explosive Test Table C-1 FORM ONES 205 2 j80
)
C
DOCUMENT NO P
pAGE OF NUCLEAR ENERGY SERVICES, INC.
Valve Test.
2 NMPC field ~ 'ES Sys t,em I.D. a 1 Test. Limits Freq. test general
- t. Req's. procedure procedure Containment 93-09 ET by NMPC 81A0015 Spray 93-10 by NMPC 8IA0015 93-11 ET by NMPC 81A00 1,5 93-12 . by NMPC 81A0015'RT 2
Leak Rate Test. C Cyclic (every scheduled ET/p P ar t-stroke Exercise Testing refueling outage)
ET Full-.stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Q Quarterly PIT Position Indicator Test Bi-weekly FST Fail Safe Test XT Explosive Test Table C-1 FORM -. NES 205 2/80
C 81A0416 DOCUMENT NO.
~ ',. NUCLEAR ENERGY SERVICES, INC.
PAGE,C12 PF 20 Valve Test NMPC field NES 2
System T..D. 1 Test Limits Freqo test .
general R~q's. procedure procedure Core 81-73 C SRT Setpoint=75 psig 2C by NMPC 81A0015 Spray 81-70 C SRT Setpoint=75 psig 2C by. NMPC 81A0415 81-75 C SRT Setpoint=75 psig 2C by NMPC 81A0015 81-76 C SRT Setpoint=75 psig 2C 'y NMPC 81A0015 81.-11 C SRT Setpoint=320 psig 2C by NMPC 81A0415 81-31 SRT.. Setpoint=320 psig 2C by NMPC 81A0015 C SRT Setpoint=60 psig 2C by NMPC 8IA0015 81-78 Setpoint=60 psig 2C by NMPC 81A0015 81-79 Setpoint=60 psig 2C by NMPC 81A0415 SRT'RT 81-80 Setpoint=60 psig 2C by NMPC 81A0015 C
LRT Leak Rate Test 2 C Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Eull-stroke Exercise Testing 2C Once every two- cycles SRT Safety Relief Test Q . Quarterly PIT Position Tndicator. Test Bi-weekly FST Fail Safe Test ZT Explosive Test Table C-1 FORt/ = NES 205 2/80
C
~OF~
DOCUMENT NO.
PAGE NUCLEAR ENERGY SERVICES, INC.
Valve Test 2 NMPC field NES System I.D. 1 Test Limits Freq. test general Rea's. procedure procedure Containment 80-01 ET Stroke time=70 sec N 1-ST-Q5 81A0412 Spray 80-02 Stroke time=70 sec N 1-ST-Q5 81AOII 12 80-21 ET Stroke time=70 sec Nl-ST-Q5 81A0012 80-22 Stroke time=70 sec N 1-ST-Q5 81A0012 80-15 ET Stroke time=60 sec. Nl-ST-Q5 81A0012 80-16 Stroke time=60 sec N1-ST-Q5 81A0412 80-35 Stroke time=60 sec N1>>ST-'Q5 81A0412 80-36 ET Stroke time=60 sec N1-ST-Q5 81A0012 80-05 ET by NMPC 81A0015 80-06 ET by NMPC 81A0415 80-25 ET by NMPC 81A0015 80-26 by.NMPC 81A0015 90-21 90-22 90-23 90-20 2
LRT Leak Rate Test C Cyclic (every scheduled-ET/p Part-stroke Exercise Testing refueling outage)
ET Eull-stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Q Quarterly PI: Position Indicator Test, Bi-sleekly FST Fail Safe Test XT Explosive Test Table C-1 FORM =.. tv'"S 205 2/80
DOCUMENT NO. S 0 NUCLEAR ENERGY SERVICES, INC. PAGE ~OF~
Valve Test 2
NMPC field NES System Z.D. 1 Test Limits Freq. test general Req's. procedure procedure Containment 93-25 ET No stroke time Nl-ST-Q5 81A0012 Spray limit Raw Water 93-26 No stroke time Nl-ST-Q5 81A0012 limit 93-27 ET No stroke time Nl-ST-Q5 81A0012 limit 93-28 ET No stroke time Nl-ST-Q5 81A0012.
limit FA E LRT Leak Rate Test 2 C Cyclic (every scheduled ET/p Part-stroke Exercise Testing refueling outage)
ET Full-stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Quarterly PIT Position,Indicator Test Wb Bi-weekly FST Fail Safe Test XT Explosive Test Table C-1 FORM 8NES 205 2/80
DOCVIVIENT NO.
PAGg C15 PF .20 NUCLEAR ENERGY SERVICES, INC.
Valve Test 2
%PC field HES System I.D. 1 Test Limits Freq. test general Req's. procedure procedure:
Liquid NP- I Poison 05A D XT C N1-MST-C2 81A0010 05B D XT C N1-MST-C2 81A0010 00A SRT Setpoint=1000 psig 2C by NMPC 81A0015 04B SRT Setpoint=1000 psig 2C by NMPC 8IA0015 39-01 ~-
39-02 'I-60.1-14 C'y 15 16 17 00-03 by NMPC 81A0415 00-13 by NMPC 81A0415.
02-19 NMPC 81A0015 02-20 by NMPC 81A0015 1
Leak Rate Test 2 LRT C Cyclic (every scheduled ET/p P art-s t roke Exercis e Tes ting refueling outage)
ET Full-stroke Exercise Testing 2C Once every two cycles SRT Safety Relief Test Q
. Quarterly PIT Position Indicator Test Vb Bi-sleekly FST Pail Safe Test, XT Explosive Test Table C-1 FORM -.. NES 205 2/80
~ 44 78II j'
DOCUMENT NO..
NUCLEAR ENERGY SERVICES, INC.
Valve PAGE ~OF~ t Frequency C Field Tes rocedure System Number Requirements
.Quarterly N 1-ST-Q0 Cleanup 33-01 Exercising 33-02 33-00 Test'mergency Condenser 39-09 39-10 39-07 39-08 CV-NC-11 NC-12 39-11 Exercising Test, 39-12 Fail-Safe Test 39-13 39-10 N1-ST-Ql Core Spray 81-01 Exercising Test 81-02 81-21 81-22 00-05.
00-06 00-02 00-12 00-01 00-09 00-10 00-11 93-51 93-52 TABLE C-2 FORM ~ NES 205 2/80 .
~'
~GP~
DOCUMENT NO.
l PAGE NUCLEAR ENERGY SERYICES, INC.
C Field Valve Tes r.
Frequency rocedure 'System Number Requirem'ends Quarteriy N 1-ST<<Q5 Contairiment Spray 80-01 Exercising Test (Cont'd) 80-02 80-21 80-22 80-15 S0-16
&0-35 80-36 Containment Spray 93-25 Raw Water 93-26 93-27 93-28 93-09 93-10 P 93-11 93-12 Nl-ST-M2 Emerg. Cond Make 60-17 Up 60-18 by NMPC Core Spray 81-07 81-08 81-27 81-28 Containment Spray 80-05 80-06 80-25 80-26 Liquid Poison 02-19 II2-20 Emer. Service Water 72-66 72-77 72-78 72-79 1'ABLE 68-01 68-02 68-03 68-00 C-2 FORM NES 205 2/80
=..
DOCUMENT NO.
NUCLEAR ENERGY SERVICES, INC.
Valve PaGE ~OP~ t C Field Yes Frequency rocedure System Number Requirem'erits Bi-vIeekly N1-ST-V4 Main Steam 01-01 part stroke 01-02 Exercising Test 01-03 01-04 Feedwater 31-03 31-00 TABLE C-2 FORtd =,N=S 205 2/80
DOCUMENT NO. S O4 e
~
NUCLEAR ENERGY SERVICES. INC.
~ ~
p~sa ~or- ~0 Frequency C Field Valve Tes t rocedure Number Requirem'ents Every 2 cycles by NMPC Main Steam N?A Safety Relief Test N7B N7C N7D N7E N7F .
N?G.
N?H N?3 N7K N7M N7N N?U N7R N7S N7T Core Spray 81-73 81-70 81-75 81-76 81-11, 81-31 81-77 81-78 81-?9 81-80 Liquid Poison ~ NPOOA NPOWB
~ 4 a 4 TABLE C-2 FORM% N'ES 205 2/SO
DOCUMENT NO, 81A0416 E
NUCLEAR ENERGY SERVICES, INC.
PAGE ~2pP Ep C Field Valve Yes t Frequency rocedure System Number Requirements Cyclic N 1-ISP-25.1 Main Steam 01-01 Leak Rate Test 01-02 01.-03 01-00 N 1-ST-C2 NR-108 Safety Relief Test A thru F Nl-ST-R8 01-01 Exercising Test, 01-02 Position Indicating Test, 01-03 Exercising Test, 01-00 Fail-Safe Feedwater 31-03 Exercising Test, 31-00 Position Indicating Test Shutdown Cooling 38-01 38-13 38-02 Exercising Nl<<MST-C2 'iquid Poison NP05A Test'xplosive Test NP05B C
N 1-ST-Q4 Cleanup 33-01 Position Indicating 33-02 Test Emergency Condenser 39-05 Exercising Test, 39-06 Fail-Safe
~
I Nl-ST-Ql Core Spray 00-01 Position Indicating 00-09 Test 00-10 40-11 TABLE C-2 FORM% NES 205 2/80
gf/
DOCUMENT NO.
E PAGE O> OF NUCLEAR ENERGY SERVlCES, INC.
APPENDIX D GENERAL TEST PROCEDURES
~ ~ ~
FORM NES 205 2/80
t II
'83A0416 DOCuMENT NO PAGE OF NUCLEAR ENERGY SERVICES, INC.
APPENDIX D GENERAL TEST PROCEDURES The documents listed below cover general guidelines for the, inservice testing of safety-related Class 1, 2 and 3 pumps and valves. They provide summaries of Section XI testing requirements, including coverage, type and frequency of tests, acceptable test limits, instrument requirements, data collection, evaluation of data and records.
NES Document No. Title NES 81A0010 General Procedure for ASME,Section XI Inservice Testing of Pumps 81A0011 General Procedure for ASME Section XI Inservice Testing of Valves, Category A Valve Leak Rate Test 81A0012 General Procedure for ASME Section XI Inservice Testing of Valves, Category A, B, and C Valve Exercising Test 8IA0013 General Procedure for ASME Section XI Inservice Testing of Valves, Valve Position Indicator Test 81A0010 General Procedure for ASME Section XI Inservice Testing of Valves, Explosively Actuated Valve Test
.'::-81A0015 . ~ -
General Procedure for ASME Section XI Category C
'afety and Relief Valve Test General. instructions for data. collection and preparation of data sheets, the evaluation of the data, and record management for the pump and valve tests are incorporated into these documents for optional use by Nine Mile Point Unit 1 personnel. These instructions, as well as forms, may be modified or replaced by approved equivalents to accommodate existing plant surveillance and maintenance procedures that fully comply with the requirements of Section XI. Other pump- and valve-specific
'nf orm ation, such as hydraulic circuitry, actual test set-up and perf orm ance, precautionary measures, etc. are outlined in Field Test Procedures listed in Appendix F.
FORM = NES 205 2/80
C DOCUMENT NO. 8~04'~
PAGE Ei OF NUCLEAR ENERGY SERVICES, INC.
APPENDIX E RECORDS FORM -" NES 205 2/80
C DOCUMENT NO. 81A0416 E2 =2 PAGE OF NUCLEAR ENERGY SERViCES, INC.
RECORDS Per Section XI, IWP-6000 and IWV-6000, summaries of the inservice testing programs for all pumps and valves should be maintained in a format that portray their current status.Section XI also requires the maintenance of test records, component records and records of corrective action. The General Test Procedures of Appendix D include forms that are designed to fulfill these requirements and primarily intended for program control, analysis and comparison, establishment of reference values, and documentation compliance. Test data, wherever required to be entered, may be transferred from data sheets used in the Field Test Procedures. The results of the analysis will be reflected in the "Test Results" section of the Field Test Procedures.
The following forms are attached to Appendix E and are duplicated from appropriate General Testing Procedures of Appendix D.
Figure 1 Pump Summary Sheet .
Figure 2 Pump Data Sheet Figure 3 Pump Reference Data Sheet Figure 0 'ump Analysis Sheet Figure 5 Valve Summary Sheet Figure 6 Valve Leak Rate Test Sheet Figure 7 Exercising Test Data Sheet Figure 8 Valve Position Indicator Test Data Sheet
,Figure 9 ....'ategory D Explosively Activated Valve Test Sheet Figure 10 Category C Safety and Relief Valve Test Data Sheet FORM 8 NES 205 2/80
C ASME SECTION XI INSERVICE TESTING PUMP
SUMMARY
SHEET Pump ID System Page Manufacturer Model Serial No. Field Test Proc. No.
Test Ref.
Successful Req'd Data Test. Test'ate Action Comments Set No. Accep. Al ert Range No.
Range Range "Q NVMEAQ ENECIQV SK41~CTS le@
FIGURE 1
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~ 4
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RRSL
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LLEW ewmm SLSL
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~ 0
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ASHE SECTION XI INSLRVICE TESTING VALVE
SUMMARY
SHEET Valve ID Size TYpe Category System Manufacturer Hodel Field Test Proc. No./Rev. Page Test No.
1 Date Pass Fai 1 Rema rks.
(>) LR- Leak Rate Test ET Exercising Test PIT Position Indicator Test SRT Safety Relief Test XT Explosive Test Fig. 5 9 tlvCLEAH EHE'R~Y SF$ cvCKS t.'>C
4 ASME. SECTION XI INSERVICE TESTING CATEGORY A VALVE LEAK RATE TEST (LPT) DATA SHEET Val ve ID Size Type S>s'tern Manufacturer Model t No LRT-. Date Field Test Proc. No./Rev.
PART I Leaka e Measurement Test DP Permissible psi Nedium Temp.
ml /h (wa te r)
'.v Measured ml/h (water)
Leak Rate: scfd (air) ', Leak Rate: scfd (a i r)
If Valve(6", go to
SUMMARY
. I f Valve>6", complete Parts 2 and 3.
PART 2 Margin Calculation MR" LR NR Maximum Permissible Leak Rate MR - PR LR Measured Leak Rate (Thi s Test)
PR Measured Leak Rate (Prev ious Test)
Check one : R ~ 0.5 (Pass)
R ~ 0.5 (Fail)
PART 3 Projection Calculation Estimate projected rate for next test if:
(1) At least 3 successive tests have passed, and (2) Lea kagre rates increase w i th time.,
Projected leak. rate for next test (check one) : Rot Applicable ml/h (water) scfd (air)
She'ck one: Projec,ion below 1.1 x llR'Pass)
Projection above I.l x HR (Fail)
(over)
Fig. 6
/Jsf'UCLEAR 'ENERGY SEA'ACES lNC
C s
s7 CATEGORY A VALVE LEAK RATE TEST (LRT) DATA SHEET (Cont.)
SUMMARY
OF RESULTS.
Review of Data indicates that valve leak parameters are within allowable limits Pass Fail PART 1 Leakage Measurement Valve PART 2 Margin Caicuiation
>6" only PART 3 Projection Caicuiation l f 7,. descr ibe correct ive act ion 1
.Re-Test No. Re-Test Date (1) Attach Data Sheet confirming test of satisfactory operation subsecuent to corrective action taken.
Signature(s) and Title(s) of Date Person(s} responsible for Test Fige 6.1 fp eo M PtUCt.EAia E7SERCY $ aPVCFS Is'C
E ASHE SECTION XI INSERVICE TESTING CATEGORY A AND B VALVE AND CATEGORY C CHECK VALVE EXERCISING TEST (ET) DATA SHEET Valve ID Size Type Category System Manufacturer Model Test No. Date Fi el d Test.
(from Field Test Proc. No./Rev.
Procedure)
PART 1 Stroke Test Part-stroke test Test successful Full-stroke test Test not successful If Category C Check Valve, go to" SUM1'IARY OF RESULTS PART 2 Power-operated Valve (Category A and B only) i; Stroke Time Measurement Measured Stroke Time sec Limi ting Value of Stroke Time sec iieasured stroke time shorter than or'qual to imiting1 time (Pass) iieasured stroke time longer than limiting time (Fail) ii. Increase in Stroke Time Measured stroke time (this test) sec Measured stroke time (previous) sec If .Limiti'ng Stroke Time ~ 10 .sec, check one R <<1.5 (Pass)
R a 1.5 (Fail)
If Limiting Stroke Time w 10 sec, check one SEPAL R ~1.2SO(pass)
R ) 1.25 (Fai))
PART 3 Fail-Safe Valve (Category A and B only)
\
Did valve test satisfactorily on loss of actuator power ?
': Yes No (over) r.Q NUCLEAA ENRAGY c5.1!Sm Fig.7
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5 ~
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C ASHE SECTION XI'NSERVICE TESTING CATEGORY D EXPLOSIVELY ACTUATED VALVE TEST (XT) DATA SHEET Valve ID Size TYPe SYstem Hanufactu'rer Mode1 XT-
, Test No. Test Date Field Test
( from f i el d Proc. No./Rev.
test procedure)
Number of Old Charge(s) Tested Batch No.
Charge Fired Charge Failed to Fire Batch No. of Replacement Charge (s)
If any charge(s) failed to fire, describe corrective action l Re-Test No'. XT- Re-Test Date (1) Attach Data Sheet. confirming test of satisfactory operation suhseauent to corrective action taken.
Signature(s) and Title(s) of Date Person(s) responsible for Test Fig. 9 p O'LiC l.EAR ENERGY SeRVICES )p<C.
ASME SECTION XI INSERVICE TESTING CATEGORY C SAFETY AND RELIEF VALVE (SRT) DATA SHEET Val ve I D Size Type System Manufacturer Model Test. No. Test Date Field Test Proc.'oa/Rev.
Valve Tested In-Place Valve Bench-Tested Pressure required to lift valve pslg Allowable range of set-point psig Review of Data indicates that the valve tested satisfactorily Yes No If No , describe corrective action Re-Test No Te-Test Date
{1) Attach Data Sheet confirming test of satisfactory operation subsequent to corrective action taken.
2.
Signature(s) and title(s) of Date Person(s) responsible for Test Fig. 1O 0 NJC'-s Iltv IICYssll"d Cf'5 Ilia
."I ~
I DOCUMENT NO, NUCLEAR ENERGY SERVlCES, lNC. PAGP Fl QF 2 APPENDIX F FIELD TEST PROCEDURES FORM = NES 205 2/80
DOCUMENT NO. 8~04i8 NUCLEAR ENERGY SERVICES, INC. PAGE P2 GF~
FIELD TEST PROCEDURES The following Nine Mile Point Field Test Procedures are part of the Pump and Valve Inservice Testing Program.
Procedure No. T.itle Nl-ST-Ql Core Spray Pumps and Motor Operated Valves Operabiity Test N 1-ST-Q6 Containment Spray and Raw Water Pumps Operability Test Nl-ST-Q2 Control Rod Drive Pumps Flow Rate Test Nl-ST-M 1 Liquid Poison Pump Flow Rate Discharge Pressure Test Nl-ST-M0 Emergency Diesel G.enerators Manual Start and One Hour Rated Load Test Nl-ST-QO Reactor Coolant System Isolation Valves Exercising Test Nl-ST-Rs Reactor Coolant and Piimary Containment Isolation Valves and Timing N 1-ST-Q5 Primary Containment isolation Valves Exercising N 1-MST-C2 Liquid Poison Squib Valves Test Firing and Inspection Nl-ST-V0 Feedwater and Main Steam Line Power Operated Isolated Isolation Valves Exercise Test N 1-ST-C2 Manual Opening of the Solenoid-Actuated Pressure Relief Valves and Flow. Verification N I-ISP-25.1 Main Steam Isolation Valves Leak Rate Tests N 1-ST-M 2 Emergency Cooling System Makeup Tank Level Control Valves Exercise Tests FORM NES 205 2/80
'I cX.