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 g
I C'
12/29/78 12/14/79 12/31/80 6/)2/8]
Approved by Mg of Proj's M r ISI.Eng QA Mgr LI 8i08140368 8i0807'
=PDR,. ADOCK 05000220 4 P
'~DR NUCt EAR ENBACVSKRV!CES.'NC.
RECORD OF REVI'SION I 81A0416 Rev No Date Description Reason Prepared by Approved by 12/29/78 12/14/79 1 2/31 /8 See CRA 564 See CRA 1132, See CRA 1653 NMPC Comments NMPC Comments.
Corrections to Plan.
Reflect as built data.
CRA-1132 NRC comments from LO/80 meeting; complete'ocument revision and format changes.
6/iz/S>
Extensive Revision Sec CRA 1903 Zncorporate NRC and NMPC comments.
gg NUCLEAR EhFPGY SERVtZFS. INC.,
DpCUMENl Np 81 0416 NUCLEAR ENERGY SERVICES, INC.
PAGE~OF~
TABLE OF CONTENTS 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
~Pa e 0.
Appendices A
B C
D E
F Pump and Valve List Valve Relief Requests Test Schedules General Test Procedures Records 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
~
NUCLEAR ENERGY SERVICES, INC.
'OCUMENT NO Slap PAGE 5
OF 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 NUCLEAR ENERGY SERVICES, INC.
PAGE OF 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 willcommence 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
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO 81A0416 PAGE OF 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 willachieve 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,
NUCLEAR ENERGY SERVICES, INC.
DpCUMENT Np 81A0416 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 VALVELIST 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 identifies the selected pumps and valves with all additional F
information, including reiief requests, required by the "NRC Staff Guidance".
3.2 VALVERELIEF 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 NUCLEAR ENERGY SERVICES, INC.
PAGE E
OF 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
4 NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO 81A0416 PAGE Z 1 OF 37 APPENDIX A PUMP AND YALVELIST FORM ONES 205 2/80
DOCUMENT NO 81A0416 NUCLEAR ENERGY SERVICES, INC.
PAGE OF 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
A a
NUCLEAR ENERGY SERV(CES, INC.
DOCUMENT NO SM0416 pAGE
~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 a
NUCLEAR ENERGY SERVICES, INC.
DpCUMENT Np 81A0416 PAGE 4
QF 37 TABLE 1 ABBREVIATIONSUSED IN VALVELIST
~Valve T e
G Gate/Globe R
Relief SC Swing Check E
Explosive Normal Position 0
Open C
Closed LO Locked Open LC Locked Closed Actuator T e
E AC current Motor Operated DC current Motor Operated Air-piston Operated Electro-Mechanical Self-Actuated Air-Diaphram Manual Explosive LRT ET ET/P PIT SRT XT FST Test Re uirement Leak Rate Test Exercising Test (including stroke time, unless otherwise noted)
Part-stroke Exercising Test Position Indicator Test Safety/Relief Test Explosive Test Fail Safe Test FORM ONES 205 2/80
0 zm CO CI tA O
System Core Spray Core Spray Topping Containment Spray Cont. Spray Raw Water Liq. Poison CRD Pumps Pump ID 1 1 1, 112 121, 122 ill, 112 121, 122 111, 112 121; 122 111, 112 121, 122 NP 02A NP 02B ll, 12 Quality P R ID Group Freq.
Measured Parameter N
p.
6PQ V. Tb 18007 Q6 2
3 X,X 5
18007 B
Q6,7 x
x x
18012 B
Q6 2
3 x x
5 18012 Q6 2
3 x x
5 18019 B
M7 x
x x x
x 18016 B
Q6$ 7 2
3 x x
x TABLE2 LIST OF PUMPS FOR INSERVICE TESTING Field Test Proc. No.
Nl-ST-Q 1 Nl-ST-Q 1 Nl-ST-Q6 Nl-ST-Q6 Nl-ST-M1 Nl-ST-Q2 Zi zCn m
m Q
COm C
Om (8
X O
Diesel Cooling
. Raw Water 102, 103 18026 C
x x
Nl-ST-MO 1
Constant speed drive, test at nominal nameplate speed.
2 Constant Pi assumed, water level recorded for reference.
3 Fixed resistance system, flow to be measured only.
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-Opo m
Z 0
p
I
Cor d Relief
- o. 18002 DOCUHENT NO.
81AO/3 PAGE A 6 37 Vaiye
- Ho..
I/I 4l
/IL OL00 Va1ve Category 8
C D
4lN 4l
/4)
I0 JJ
'O 0
0 JJ I/I0 0
JJc 4l L
O l/l 0 4l 4l 4l O4l QC Remarks 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%
=. 1236 psig + 1%
N7F 6
R SA C
SRT Setpoint = 1218 psig + 1%
Q N7G
%NO f
N7H D
~ N73
$ N7K 6
R 6
R 6
R 6
R SA C
SA C
SA SA C
SRT SRT SRT SRT Setpoint = 1227 psig + 1%
Setpoint = 1205 psig + 1%
l Setpoint = 1218 psig + 196 I
Setpoint = 1236 psig + 1%
N7M 6
R SA SRT Setpoint = 1218 psig + 196
Core d Relief
- o. 18002 DOCUHENT NO.
81A0416 "j
PAGE A 7 37 Valve
- No..
IA 4l IgC O
I00 LJ Valve Category B
4lN III 4I Ig)
I0 IgD 4J U
C0 UI0 IgE I0 C
L Vl Cr 4l 4l IL 4lD 0'l IC Remarks 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
Fe er
- o. 18005 DOCUMENT NO.
PAGE 81A04 A 8 5'7 Valve
- Ho,'.
I/I IO IOA oI00 Va1ve Category 8
C D
III N
Ijl Cl lO)
I0 D
0 A0 4J III 0
IA III EA0 A
III 0 Ol Q
Remarks 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 1)0 Vl
Ma P
- o. 18002 DOCUMENT NO.
81A PAGE Va)ve
- Ho.'-.
IA 4l 4lC 0I-00 LJ Va Ive Category I
8 C
D 4l OC 4lN V) 4l 4)
L0
'D U
0 4J Vl0 CL, IDEL0 C
4lE4l I
I/I 0 4l 4l OC Remarks 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 c~ 01-02
~ 01-03 nC 3 01-00 20 G
MO A 20 G
MO-A 20 G
AO 20 G
AO 0
.LRT,ET PIT LRT,ET PIT 00 00 00 00 Stroke time = 10 sec, Leak limit = 12.9 scfh Q 22 psig Stroke time = 10 sec, Leak limit = 12.9 scfh Q 22 psig Stroke time = 10 sec, Leak limit = 12.9 scfh Q 22 psig:
Stroke time = 10 sec, Leak limit = 12.9 scfh Q 22 psig
k
- o. 18002 DOCUMENT NO.
01A PAGE A 10 37.
Valve
- No, IA 4l IDC OI-00 LJ Va 1 ve Category 8
C-D 4l O
C 4lN Ijl 4l II)
L.0 O
0 C0 Vl0 0
IOEI0 C4lE4l I
P O
N O
4l 4l cK 4lO O4l OC Remarks'R-108A B
X X
EM C
X X
'EM C
X X
EM C
X X
6 R
EM C
'X X
6 R
EM C
X X
6 R
EM C
%50 z 30-02
~ 66-07 n
66-08 fi 66-09 2
G 2
SC 10 R
10 R
10 R
SA C
ET ET SRT SRT SRT 08 LRT as per'App. 3 03 LRT as per App. 3 Added Spring '8l Outage Added Spring '81 Outage Added Spring '81 Outage
P
. 18002 DQCUHENT NQ 81A04 PAGE A 11 37 Va 1 vs
- Ho'.
I/l 4l IQ 6
O 100 LJ Valve Category A
8 I/I6 OC N
61)
Ol c4)
I0 4J0 C0 Vl0 0
60E I0K Cill6 OlI-Iil 0'l4l CC Remarks 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 66-16 10 10 R
SA C
R SA C
SRT SRT Added Spring 1981 Outage Added Spring 1981 Outage I
66-l7 nZ
~ 66-18 f
10 10 R
SA C
R
-SA C
SRT SRT Added Spring 1981 Outage Added Spring 1981 Outage
P
- o. 18009 DOCUMENT NO.
8lA04l6 PAGE A 12 Va1ve
- Ho.-
Vl Cl lg C
I-00 Va 1 ve Category A
B N
4)
CO) 0 4J U
Q 5
L I/l O lO dl nC Remarks 33-02 33-00 33-01 33-03 X
SC MO-AC 0 MO-AC 0 MO-AC 0 SA 0
'T ET, PIT ET Stroke time = 18 sec.
LRT as per App. 3.
Stroke time = 18 sec.
LRT as per App. 3.
Stroke time = 18 sec.
LRT as per App. 3..
LRT as per App. 3.
D Dn Sn
C
Dry d Torus PRI 18006 DDDDNENT NO.
E1A0416 PAGE A 13 37 Valve
- Ho..
201.2-25 201.2-26 201.2-27 201.2-28 201.2-29 201.2-30
~
20!.2-23 RQo
~ 201.2-20 83.1-09 R 83.1-10 443 4l)
ID C
0 00 EJ Valve Category B
C D
G M
G M
G M
G M
G M
Yi G
M 0
G MO AC 0
G AO 0
Vl0 43 EDEL0 C
ET C
ET C
ET C
ET C
ET C
ET C
ET C
ET 0
ET 0
ET G
4ll 5
Ul O
4ll Cl 4llD U'll OC LRT as per App. 3.
Stroke Time = 60 sec LRT as per App. 3.
Stroke Time = 60 sec LRT as per App. 3.
Stroke Time = 60 sec LRT as per App. 3.
Stroke Time = 60 sec LRT as pe) App. 3.
Stroke Time = 60 sec LRT as per..App. 3.
Stroke Time = 60 sec LRT as per App. 3.
Stroke Time 60 s'ec LRT as per App. 3.
Stroke Time = 60 sec LRT as per App. 3.
Stroke Time = 60 sec LRT as per App. 3.
Stroke Time = 60 sec Remarks
- 83. l-l l 0
G MO-AC I RT as per App. 3.
Stroke Time = 60 sec
Dry lid Tor Us Pd(I 18006 DOOONENE NO.
81AOA1',iAGE A 14 37 Valve
- Ho..
N 4l 111C Q
00 CJ Val ve Category OlN V) 02o.
I-E0 D
4J U
c0 EJ Ih0 0
C 11) 5 Ul O
Ol I f-EE Remarks 83.1-12.
201-07 201-08 20 20 G
AO 0
,G MO AC 0 G
AO 0
ET ET ET 10 10 LRT as per App. 3.
Stroke Time = 60 sec LRT as per App-3.
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 5 201-31
~g 201-32.
D
>s 201 2 32 20 MO-A 0
G MOA 0
G MOA 0
G MO-D 0
ET ET ET 10 10 10 10 LRT as per App. 3.
LRT as per App. 3.
LRT as per App. 3.
LRT as per App. 3.
~,J e
Dry d Torus PRI 18006 DOCUMENT NO.
Sl PAGE A 15 37 Va 1 ve
- Ho..
fo C
Ol00 ED Va 1 ve Category A
B C
OlN Vl Ol IO)
L,0 D
4J0 C0 Vl0 62 ill E
S0 Remarks 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.
'01.2-33 MO-DC 0 ET 10 LRT as per App. 3.
201.2-39 201.2-00 SC SC SA 0
SA 0
ET 16 LRT as per'pp. 3.
16 LRT as per App. 3.
201.2-67 3/0 SC SA 0
ET 16 LRT as per,App. 3.
+
201.2-6S p 201.2-70
~ 201.2-71 I>> 68-01 Pi 3/0 3/0 3/0 30 SC SC SC SC SA 0
SA SA 0
AO 0
ET ET ET ET 16 LRT as per App. 3.
16 LRT as per App. j.
16 LRT as per App. 3.
68-02 30 SC AO 0
Dryw d Torus Pdcl 18006 DOCUMENT NO.
PAGE A 16 Bl 37 Valve
- Ho..
Vl OlIJ (D
C 0l-00 LJ Va l ve Category A
B C
Cl Ig O
Q.
I-t0 0
C0 4J Ih0 n
IDEl0 5
4J 8
Cl I-aC Remarks 68-03 30 SC AO 0
ET 68-05 68-06 30 30 SC AO SC AO 0
ET 0 ET'RT as per App. 3 LRT as per App. 3 68-07 30 SC AO 0
ET LRT as pej App. 3 68-08
~
68-09
'c 68-10 D
Dn D
30 30 30 G
AO G
AO AO 0
ET 0
ET 0
ET 13 13 13 LRT as per, App. 3 Stroke time = 5 sec.
LRT as per App. 3 Stroke time = 5 sec.
LRT as per App. 3 Stroke time = 5 sec.
Dryw d Torus PRI 18010 DOCUMENT NO.
8
'., 6 PAGE A
37 Valve
- No.'.
III Ci CIC 0I-00 Valve Category C
D IA Cl 0C ClN Vl Cl Ig)
I0 0
C0 4J VI0 0
I 0
G 5
PIII 0'l Cl i-cC Remarks 201.7-01 201.7-02 201.7-03 201.7-00 201.7-08 201.7-09 201.7-10
~ 201.7-11
< 201.2-109 201.2-110 f
D D
D D
D D
1 G
1 G
1 G
1 G
1 G
1 G
1 G
3/ii G
3/0 G
AO AO AO AO AO AO AO AO AO AO ET ET ET ET ET ET ET ET 13 13 13 13
.Stroke time = 60 sec.
LRT as per App. 3 Stroke time = 60 sec.
LRT as per App. 3 Stroke time = 60 sec.
LRT as per App. 3 Stroke time = 60 sec.
LRT as per, App. 3 Stroke time = 5 sec.
LRT as pe'r App. 3 Stroke time = 5 sec.
LRT as per App. 3 Stroke time = 5 sec.
LRT as per App. 3 Stroke time = 5 sec.
LRT as per App. 3 Stroke time = 60 sec.
LRT as per, App. 3 Stroke time = 60 sec.
LRT as per App. 3
Drywe d Torus PdcID 13010 DOCUMENT NOe SlA043 PAGE A ls OF Valve
- Ho..
Vl Ol tOC o
L.00 Valve t:ategory N
EA Ol ID O
I-0 ID 4J O
0 4J 0
0 tg EL0 D
O 4)
OC Remarks 201.2-111 201.2-112 D
D 3/0 G
'AO 0
ET G
AO 0
ET Stroke time = 60 sec.
LRT as per App. 3 Stroke time = 60 sec.
LRT as per App. 3
?C D
m?
Dn
r
Shu PR
. 18018 DOCUMENT NO.
81AO ~,"'.
PAGE A 19 37 Valve
- No..
Ih 4l 4J fOC o
00 EJ Va l ve Category IDN Eh 4) lg)
L0 D
4J O
C0 Vl0 0
EL0 Remarks 38-01 10 G
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
y Cooling
. 18017 DOCUMENT NO.
8 PAGE' 2
OF 37 Valve
- Ho, N
4) lg C
oL.00 Va l ve Category A
B Q
O Ol C)
I0 D
U C0 4J IA0 CL E
L0 CSC PN Ct 4J 4J OC D00 CC Remarks 39-09 39-10 MO-AC 0 MO-AC 0 ET ET LRT as per App. 3 Stroke time = 38 sec.
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 39-06 60-17
%50
~ 60-18 P
E 39-01 g~ 39-02 Z
AO C
AO C
AD C
AD C
M ET, FST ET, FST ET ET LRT as per App. 3 Stroke time = 60 sec.
I LRT as per App. 3 Stroke time = 60 sec.
Stroke time = 10 sec.
4 Stroke time = 10 sec.
r
Em y Cooling DOCOHENT NO.
81A0416 PAGE A 21 0
Valve
- Ho.'.
III III III C
'o I00 EJ Val ve Category A
B C
III OC III III)
I0 III 4J U
C0 III0 C4 III EI-0 CQ 5
lh Ct Ol 4)
OC Remarks 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
39-12 1
G AD AD ET, FST ET, FST 13 13 LRT as per App. 3 Stroke time = 5 sec.
LRT as per App. 3 Stroke time = 5 sec.
39-13 g 39-10 g 60.1-10 a
3 60.1-15 I
G AD AD L
ET, FST ET, FST 13 13 LRT as per App. 3 Stroke time = 5 sec.
LRT as per App. 3 Stroke time = 5 sec.
DOCUMENT NO 81A041 Eme y Cooling Pdc
. 18017 PAGE A 22 7
Valve
- No.'.
60.1-16 lh lO IQ C
oI00 Va Ive Category A
B 6
OC 0N CL 4l IO O
C I
l/l Q' 4)
O 4)
OC Remarks 60.1-17 G
M L
05-01 G
AO ET 13 LRT as per App. 3 Stroke time = 5 sec.
05-02 05-03 G
AO G
AO ET 13 13 LRT as per App. 3 Stroke time = 5 sec.
LRT as per App-3 Stroke time = 5 sec.
05-00 G
AO ET 13 LRT as per App. 3 Stroke time = 5 sec.
Liq ison
. 18019
. DOCUMENT NO.
81AI.-'..
PAGE A
P d7 Valve
- l3o.'.
IA 4J 4IC 0I00 Va 1 ve Category 4l OC 4I IO)
I0 III D
4J0 C0 Ol0 II E
Ig I0 C
4IE 4I I
PI/l 0 Ol 4I f-oC II-4l 45 ~
OC Remarks 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
Ii NP05 A I
NP05-0 D
'9 NP00-A NPOO-,B 15 E.
1Yi E
SA.
C SA C
XT XT SRT SRT Setpoint = 1000 psig Setpoint,= 1000 psig
Liq ison PR
. 18019 DOCUMENT NO.
81 PAGE A 24 37 Valve
- Ho.'.
I/l III 4J III C
'aI-00 LJ Va 1 ve Category A
B C
I/I II)
Oc III N
III IQ O
C0 Ih0 6-EI0 C
5 D
Ol 0 I2C Remarks 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
Liq iso n P
- o. 18019 Dm:UMENT NO.~81,!:.:
6 PAGE A
.: F 37 Valve
- Ho.I.'/l 4l IO C
D I00 Valve Category 8
C D
4l 0C 4lN 4l IO)
L0 IOD 4JV C0 4J 0
Ul0 II IOE I0K C
4l S.
I IA O 4l 4I Remarks 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
Dn VI
DOCUMENT NO 16 Co ay
. 18007 PAGE A
OF 37 Valve
- Ho.'.
81-01 4l lDC oL00 Valve Category C
D 4)
O C
N Vl 4)
LL I-4l Q
I0 D
V MO-A 0
IA0 CL IDE L0 ET Remarks
-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 81-08 81-27 Z
81-28
~
81-73 81-70 12 12 12 12 3/
3/
SC S
R SA SA SA SA SA SA ET ET ET ET SRT SRT Simultaneous with pump testing (3'000 gpm)
Simultaneous with pump testing (3000 gpm)
Simultaneous with pump testing (3000 gpm)
Simultaneous with pump testing (3000 gpm)
Setpoint = 85 psig Setpoint = 85 psig
0
DOCUMENT NO..
'. 416 Cor y
P
. 18007 PAGE OF 37 Valve
- Ho..
Vl 4l
/tl C
Ol00 EJ Valve Category c nF.
4l
/tl)
I0 4J U
/g El0 I/l C4lE4l I
I/l O 4l 4l CC 4-4l 4l CC Remarks 81-75 81-76 3/0 R
SA 3/0 R
SA C
SRT C
SRT Setpoint = 85 psig Setpoint = 85 psig 81-11 12 R
SA C
SRT Setpoint = 320 psig 81-31 81-77 81-78 12 R
SA 3/0 R
SA 3/4 R
SA C
SRT C
SRT C
SRT Setpoint =.320 psig Setpoint
.'60 psig I
Setpoint = '60 psig 31-79 WOO c 81-80 3/0 R
SA 3/0 R
SA SRT SRT Setpoint = 60 psig Setpoint = 60 psig g 81-09 n
P3 81-10 12 G
12 G
M n
Cor PR
. 18007 DOCUMENT NQ.
81AO PAGE A 28 37 Valve
~ Ho..
I/l Q
Io C
0 I00 LJ Valve Category A
8 Ill UC I0 lgD 4J O
c0 IIl0 Il III El0 4J CQ EQ PIIl 0 4)
OC Ill Olll Remarks 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 00-13 00-05 12 12 SC SA 0
SC SA 0
G MO-AC C ET ET ET Simultaneous with pump testing (3000 gpm)
Simultaneous with pump testing (3V00 gpm)
Stroke time = 25 sec.
00-06 G
MO AC C ET Stroke time = 25 sec.
z 93-51 P
~ 93-52 s00 02 12 12 12
.G MO-AC C G
MO-AC C G
MO-AC 0 ET ET ET Stroke time = 70 sec.
Stroke time = 70 sec.
Stroke time = 25 sec.
Cor P*
. 18007 DOCVMENT NO.
8
~
i 6
PAGE OF 37 Valve
- Ho,.'l 4)
ID C
0l-00 LJ Valve Category 8
C 4J OC 4lN Vl Ol l0)
CL I-l0 U
c0 Vl0 n
I 0
44 CQ6Q I
P D
N 0 8
Q n
OlD0 4)
Remarks 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 Valve
- No..
I/l 4l lg ol-00 EJ Valve Category C
D Vl6 UC ClN tlat I- ~
Cl,
)
I0 U
L0 IA0 Q
IDEL0 CQE Ol I
3 Ul 0 Cl tll Remarks 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 Z
> 93-17 8 93-18 12 12.
12 G
M G
M
Con ent Spray and Raw Water
. 18012 DOCUMENT NO.
~ ','16 PAGE A
F 37 Valve
- Ho..
Vlill ID C
Ol00 LJ Valve Category A
B C
N'l L0 lDD 4J0 c0 4J Vl0 0
0 Remarks 93-19 x
12 G
93-20 x
12 G
93-21 93-22 93-23 93-20
~
93-26 WSO cp 93-27 9 93-28
" 93-09 93-50 12 G
12 G
12 G
12 G
12 G
MO-AC MO-AC MO-AC MO-AC MO-AC 0
ET 0
ET 0
ET C
ET C
ET Stroke time = 70 sec.
Stroke time = 70 sec.
Stroke time = 70 sec..
Stroke time = 70 sec.
LRT as per App.3 Stroke time = 70 sec.
LRT as per App. 3
Con nt Spray and Raw Water P*l 18012 DCCUNENT NO.
(4" 416 PAGE A
OP 37 Valve
- l)0..
Vl IU IQ C
o I00 LJ Va lve Category A
8 Cl OC Ol Q)
I-.
E0 4J U
C0 4J Vl0 0
l0 GillIl-P Ih 0'J0 Remarks 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 80-19 r
SC SA 0
ET 02 80-39 X
3 SC ET 02
,PO-66 r 80-68 Dn
)80-06 Z
80-26 3
'12 12 SC SC SC SC SA SA 0
SA 0
SA 0
ET ET ET ET 02 02 Exercise during Pump Testing Exercise during Pump Testing
~ Con nt Spray and Raw Water PR
. 18012 ri~
DOCUNENT NO.
~ "'16 PAGE A
OF 37 Va) ve
- .Ho..
6738 IQc O
30 0'J Va 1 ve.
Category B
C D
O)N 613 Cl lO)
L0 f0D 43V C0 Vl0 0
6l3EL.0 C
Q 5I D
613 Ct 4l Cl EE Remarks 80-05 80-25 12 12 SC SC SA SA 0
ET ET Exercise during Pump Testing 3
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
~
60-67
%80 6 SO-65 80-15 n
f 80-16
'3 12 12 SC SC SA 0
SA 0
AO 0
AO 0
ET ET ET ET 02 02 Stroke time = 60 sec.
Stroke time = 60 sec.
Con nt Spray and Raw Water Pdr.
18012 DOCUMENT NO e Sl I.i'6 r
PAGE QF 37 Valve
- Ho.'.
Ul 4l IDC a
0
~
0 Valve Category B
C D
Ol Q)
I-L.0 0
0 4J Vl0 0
CI) 5 L
D IA Ct 4l 6 I- 05 tOD O
4)
OC Remarks 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
~ 80-02 i 80-21
'80-22 12 G
12 G
12 G
12 G
MO-AC MO-AC MO-AC MO-A 0
ET 0
ET 0
ET Stroke time = 70 sec.
Stroke time = 70 sec.
Stroke time = 70 sec.
Stroke time = 70 sec.
Class Coordinates e +
tti 0
C Size (inches)
Va l ve Type Actuator Type Normal Position Test Requirements Relief Requests OO CO h0
~
Dies erator Raw Water pa
. 18026 DOCOMENT N
'.'."."- 04l6'-
PAG 6
OP 37 Valve No..
Cl IgC 0I00 EJ Va lve Category A
8 4l 0c N
l/l C)
Cg w)
I0 D
4JV C0 I/I0 0
IQE I0 C
6 Cl I
D Vl 0 4l Q
Remarks 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 Iln ill M
I,
CR aulics
)
Pdt
. 18016 DOCUMENT "" OlA04'16 A 37 OF 37-Valve
- Ho..
IA6 IgC DI00 LJ
.Valve Category A
B 4) lg O
0 D
4J U
C0 Vl0 0
C Ol 5
Vl Q 4l Cl f-CC Remarks 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
.Stroke Time = 60 sec CV-126 3/0 AO C
07 C
p f
n
1 NUCLEAR ENERGY SERViCES, INC.
DOCUMENT NO, PAGE OF APPENDIX B VALVE:RELIEF'EQUESTS FORiVI = iNES 205 2/80
C
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
p>gE B 1 OF 10 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 NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
AGE B 2 pF'0 Valve ID RELIEF REQUEST BASIS 01 Function P R ID 02.1-02 02.1-03 Prevent back leakage from reactor vessel to the liquid poison system.
18019
'est Requirement:
Basis for Relief:
Alternate Testing:
Full stroke exercising of the valve quarterly.
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.
During every refueling outage the liquid poison system is tested.
These valves willbe exercised during,this test.
Valve ID RELIEF REQUEST BASIS 02 Function P R ID 80-17 80-18 80-37 80-38 To prevent back flow from Drywell spargers to the balance of the system when redundant loop is operating.
18012 80-19 80-65 80-66 80-67 80-68 80-39 To prevent back flow from the Torus 18012 Test Requirement:
FWl stroke exercising of valve quarterly.
Basis for Relief:
Alternate Testing:
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 woWd require pressurization of the
- drywell, necessitating shutdown quarterly.
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
DOCUMENT NO.
NUCLEAR ENERGY SERVICES, INC.
PAGE~GF~
RELIEF REQUEST BASIS 03 Valve ID Function P R ID 30-02 To prevent back flow.from the reactor vessel into the head spray system.
18002 Test Requirement:
Basis for Relief:
Alternate Testing:
FWl stroke exercising of the valve quarterly.
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 fulfillsits safety function.
This valve is leak rate tested under Appendix 3 every refueling outage.
Valve ID RELIEF REQUEST BASIS 00 FunctIan PAID 01-00 01-03 01-02 01-01 Main Steam Blocking Valve 18002 Test Requirement:
Basis for Relief:
Alternate Testing:
Full stroke exercising and stroke time verification quarterly.
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.
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 NR-108-A thru F Function Electromatic relief valves P 2 ID 18002 Test Requirement:
Full relief test exercising of valves quarterly.
L Basis for Relief: 'ull 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.
Valve ID 31-01 31-02 RELIEF REQUEST BASIS 06 Function To prevent back flow into the feedwater system from the reactor.
L PAID 18005 Test Requirement:
Basis for Relief:
Alternate Testing:
Full stroke exercising quarterly.
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.
The valves shall be integrated leak rate tested every refueling outage.
FORM ¹ NES 205 2/80
NUCLEAR ENERGY SERVICES. INC.
DOCUMENT'NO PAGE B 5 OI=
RELIEF REQUEST BASIS 07 Valve ID CV 126 CV 127
'138 Function Low sid scram control valve.
High side scram control valve.
'ooling water header check valve.
P 2 ID 18016 Test Requirement:
Basis for Relief:
Alternate Testing:
Full stroke exercising testing quarterly.
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.
Following each refueling outage all control rods are scram-'ested, following each scram from rated pressure, the mean 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.
Valve ID 30-01 RELIEF REQUEST BASIS 08 Function P 2 iD Head Spray outside isolation valve 18002 Test Requirement:
Basis for Relief:
Alternate Testing:
Full stroke'xercising test and stroke-time verification quarterly.
This valve is a normally closed passive component not required to change its position to fulfillits safety function.
The valve shall be integrated leak-tested every refueling outage.
FORMCNES 205 2/80
L NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO 81A0416 PAGE j!
E OF Valve ID ill, 112 121, 122 ill, 112 121, 122 ill, 112 121, 122 CRD 11, 12 ill, 112 121, 122 RELIEF REQUEST BASIS 09 Function Core spray injection pumps I
Core spray topping pumps Containment spray pumps Control rod drive pumps Containment spray raw water pumps PE! ID 18007 18007 18012 18016 18012 Test Requirement:
Basis for Relief:
Monthly test.
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 willbe scheduled quarterly.
Valve ID 80-00 80-01 80-03 80-00 80-V5 201-07, 08, 09~
10~
1 6~
1 7~
31, 32 201.2-32, 03, 06, 33 RELIEF. REQUEST BASIS 10 Function Containment spray and raw water system gate valve..
Drywell and torus gate valves Drywell and torus gate valves.
PE! ID 18012 18010
- 18006, 18010 Test Requirement:
Exercising of the valve from its normal position.
Basis for Relief:
Alternate Testing:
This valve is not required to, change its position to fulfillits safety function due to its passive nature.
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 NUCLEAR ENERGY SERVICES, INC.
DOCVMENT NO.
PAGE B
7 OF RELIEF REQUEST BASIS ll Valve ID 33-03 Function Prevent backflow from reactor feedwater header into reactor cleanup system.
P dcID 18009 Test Requirement:
Basis for Relief:
Alternate testing:
Full stroke exercising quarterly.
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.
The valve is included in the Appendix 3 type A leak test which is performed every refueling outage.
Valve ID 39-06 39-05 RELIEF REQUEST BASIS 12 Function Emergency cooling outside isolation valve P 2 ID l.80l7 Test Requirement:
Basis for Relief:
Alternate Testing:
Full store exercising and stroke time verification quarterly.
Full-stroke testing at power or stand by conditions would subject the plant to undue thermal cycling stress.
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 NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO, 81A0416 PAGE ~E PF 10 Valve ID
'5-01, 02, 03, 00 9-11, 12, 13; 10 68-08, 09, 10 201.7-08, 09, 10, ll RELIEF REQUEST BASIS 13 Function Containment isolation P R ID 18017 18017 18006 18010 Test Requirement:
Basis for Relief:
Alternate Testing:
Conduct trend analysis of stroke times.
Trend analysis of fast acting valves is inconclusive of valve operation due to the speed at which these valves operate.
Corrective action will'e taken if the stroke time exceeds 5
seconds.
Valve ID 58.1-01 RELIEF REQUEST BASIS 10 r
Function Core spray torus makeup isolation valve P R ID 18007 Test Requirement:
Basis for Relief:
Alternate Testing:
Full stroke exercising test and stroke-time verification quarterly.
This valve is a normally closed passive component not required to change its position to fulfillits safety function.
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' j
NUCLEAR ENERGY SERVICES, INC.
ppCUMENT Np 8>>40>6 PAGE
~
OF Valve ID RELIEF REQUEST BASIS 15 Function P k ID 38-01'8-02 38-12 38-13 Isolate reactor shutdown cooling system from reactor.
18018 Test Requirement:
Basis for Relief:
Alternate testing:
Full stroke exercising and stroke-time verification quarterly.
This valve is a normally closed passive component not required to change position to fulfillit safety function.
These valves are included in the Appendix 3, type A leak test which is performed every refueling outage.
Valve ID RELIEF REQUEST BASIS 16 Function P RID 201.2-39 201.2-00 201.2-67'01.2-68 201.2-70 201.2-71 Prevent backflow Sampling system Prevent backflow Sampling system into drywell H2-02 into torus H2-02 Prevent backflow into N2 purge-tip system 18014 18010 18-10 Test Requirements:
Full stroke exercising quarterly.
Basis for Relief:
Alternate Testing:
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.
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 A
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO 81A4016 PAGE ~BO OF 10 RELIEF REQUEST BASIS 17 Valve ID Function FR ID 39-03 39-00 Prevent reverse flow of the emergency Cooling system 13017 Test Requirement:
Basis for Relief:
Exercise test quarterly.'ull-stroke 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 NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
'AGE C1
'20 OF.
APPENDIX C TEST SCHEDUL'ES FORM -. NES 205 2/80
S NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO, 83%0416 PAGP C2 OF 20 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
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE SlA0416 OF System Valve 1.D.
Test I
Req's.
Test Limits
/
2 Freq.
NMPC field
- test, procedure NES general procedure Main Steam 01-01 A
LRT ET/p ET PIT Leak=12.9 scfh I 22 pslg 7% part stroke Stroke time=10 sec
'Wb C
C N1-ISP-25.1 N1-ST-V4 Nl-ST-RS Nl-ST-RS 81A0411 81A0412 81A0412 81A0413 01-02 A
01-03' LRT'T/p ET'IT LRT ET/p.
ET, FST Leak=12.9 scfh I 22 psig 7% part stroke Stroke time=10 sec Leak=12'.9 scfh I 22.
pslg 7% part stroke Stroke time=10 sec Wb C
C N1-ISP-25.1 Nl-ST-V4 N1-ST-RS Nl-ST-RS N1-ISP-25.1 Wb N1-ST-V4 C
N1-ST-RS 81A0411 8IA0412 81A0412 81A0413
'1A0411 81A0412 81A0412 01-04 A
NR-108 C
NR-108 C
NR-108 C
NR-108 C
NR-108 C
NR-108 C
.LRT ET/p
. ET,.
FST SRT SRT SRT SRT SRT Leak=12.9 scfh I 22 psig 7% part stro'ke Stroke time=10 sec.
'etpoint=1090 psig Setpoint=1090 psig
~
Setpoint=1095 psig l
Setpoint=1095 psig Setpoint=1100 psig Setpoint=1100 psig Wb C
N1-ISP-25.1 Nl-ST-V4 Nl-ST-RS N1-ST-C2 Nl-ST-C2 Nl-ST-C2 N1-ST-C2 Nl-ST-C2 Nl-ST-C2 8 1A041-.
18 1A04.
81A0412 81A0415
'1A0415 81A0415 81A0415 81A0415 81A0415 l LRT ET/p ET SRT PlT FST XT Leak Rate Test Part-stroke Exercise Testing Pull-stroke Exercise Testing Safety Relief Test Position indicator Test Fail Safe Test Explosive Test C
2C Q
Cyclic (every scheduled refueling outage)
Once every two cycles Quarterly Bi-weekly Table C-1 FCRM =.. NES 205 2/80
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE OF System Valve Z.D.
Test 1
Req's.
Tes t Limits 2
Freq.
lPPC field test procedure NES general procedure Main Steam N?A>>
C N?B N7C C
N?D C
N?F N7G N?H C
N?K N7M C
'7N N7U N7R G
'etpoint=1218 psig Setpoint=1227 psig Setpoint=1236 psig Setpoint=1227 psig Setpoint=1236 psig Setpoint=1218 Ps1g Setpoint= 1205 ps1g Setpoint=1254 psig Setpoint=1254 psig Setpoint=1205 Setpoint=1250 pslg psig Setpoint=1227 psig
. Setpoint=1205 psig Setpoint= 1218 psig Setpoint=1236 psig Setpo1nt=121S psig 2C 2C 2C 2C 2C 2C 2C 2C,.
2C 2C 2C 2C 2C 2C 2C 2C by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC by NMPC 81A0415 81A0015'1A0015.
81A0015 81A0015 81A0415 81'A0415 E
81A0015 81A0415 81A0415 81A0415 81A0415 81A0015 I
81A0015 81A0015 81A0015
+This test shou d be sche uled y the val e serial no.'s,.not by flan e 'loca ions.
LRT ET/p ET SRT PIT FST XT Leak, Rate Test Part-stroke Exercise Testing Full-stroke Exercise Testing Safety Relief Test Position Indicator Test Fail Safe Test Explosive Test 2
C 2C.
Q Wb Cyclic (every scheduled refueling outage)
Once every two cycles Quarterly Bi-weekly Table C-l FORM -.. NES 205 2/80
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE OF System Valve I.D.
Test 1
Req's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure Feedwater 31-03 B
31-00 B
ET/p ET'IT'T/p ET PIT 7% part stroke Stroke time=10 sec 7% part stroke Stroke time=10 sec Wb C
C Wb C
C.
Nl-ST-V4 N1-ST-R8 Nl-ST-R8 Nl-ST-V0 Nl-ST-R8 Nl-ST-R8 81A0412
- 81A0012, 81A0013 81A0012 81A0012 81A0413 68-00" C
ET 68-01 C
68-02 C
ET 68-03 C
by NMPC by NMPC by NMPC by NMPC 81A0415 l
81A0015 h
81A0015
~
81A0015 1 LRT ET/p ET'RT PET FST XT L'eak Rate Test Part-stroke Exercise Testing Full-stroke Exercise Testing Safety Relief Test Position Indicator Test Fail Safe Test Explosive Test.
2,'
Cyclic (everv scheduled refueling outage) 2C Once every ceo cycles Q
Quarterly Wb Bi-weekly Table C-1 FORMINES 205 2/80
~ '
NUCLEAR ENERGY SERVlCES, INC.
DOCUMENT NO SlA0416 PAGE G6 OF 20 System Valve I.D.
Test
.1 Reg's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure Reactor Cleanup
'33-01 ET PIT Stroke time=18 sec Q
C NI-ST-Q0 Nl-ST-Q0 81A0012
C NI-ST-Q0 Nl-ST-Qe
'81A0012 81A0013
.33-04 B
ET Stroke time=18 sec Nl-ST-Q0 8IA0412 72-66 72-67 72-68 72-69 C
ET C
ET C
ET C
ET Q
by NMPC Q
by NMPC Q
.by NMPC by NMPC 81A0015 81A0415 81A0015 I
81A0015 1 LRT ET/p ET SRT PIT FST XT Leak Rate Test Part-stroke Exercise Testing Full-stroke Exercise Testing Safety Relief Test Position Indicator Test Fail Safe Test Explosive Test 2'
Cyclic (every scheduled refueling outage) 2C Once every two cycles Q
Quarterly Vb Bi-sleekly Table C-1 FORM"-.. NES 205 2/80
DOCUlvlENTNO Sm0416 NUCLEAR ENERGY SERVICES, INC.
PAGE PF 20 System Valve I.D.
Test 1
Req 's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure Shutdown Cooling-38-01 38-13 A/
ET'38-12 A
ET Stroke time=00 sec Stroke time=00 sec Stroke time=00 sec Stroke time=00 sec C
C C
C Nl-ST-R8 Nl-ST-R8 N1-ST-R8 N1-ST-R8 Nl-ST-R8 N1-ST-R8 81A0412 8IA001,3 81A0012 8IA0013 81A0412 8IA0012' LRT'T/p ET SRT PTT FST.
XT Leak Rate Test Part-stroke Exercise Testing Full-stroke Exercise Testing Safety Relief Test Position Indica tor Test Fail Safe Test Explosive Test 2
C 2C Q
Cyclic (every scheduled refueling outage)
Once every two cycles Quarterly Bi-weekly Table C-1 FORMINES 205 2/80
I NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.,
PAGE CE QF 20 System Valve I.D.
at.
. Test 1
Req's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure.
Emer gency Condenser ET ET'9-07' ET'9-0S B
ET.
39-09 B
39-10 Stroke time=38 sec, Stroke time=38 sec
~ Stroke tim'e=38 sec Stroke time=38 sec Q
'1-ST-QO N 1-ST-Q4 N 1-ST-Q0 N 1-ST-QO 81A0412 81A0012 S1A'0012.
81A0412 39-05 B
39-06 B
39-11 39-12 B
39-13 39-10 B
ET, FST ET; FST' ET, FST ET; FST ET;..
FST ET, FST Stroke time=60 sec Stroke time=60 sec Stroke time=5 sec Stroke time=5 sec Stroke time=5 sec Stroke time=5 sec N1-ST-Q0 C
N 1'-ST-QO Nl-ST-QO N 1-ST-QO N1-ST-Q0 N1-ST-Q0 81A0012 81A0012.
81A0012 81A0012.
81A0012.
81A0012 Emergency Cond. Make Up 60-18.
B.
ET V
\\
60-17 B
ET No limit on stroke.
time.
No limiton stroke.
time-N1-ST-M2 N1-ST-M2 81A0012'1A0012 1 LRT ET/p ET SRT PIT FST XT Leak Rate Test Part-stroke Exercise Testing Full-stroke Exerci.se Testing Safety Relief Test Position Indicator Test Fail Safe Test Explosive Test 2
C 2C Q
Cyclic (every scheduled refueling outage)
Once every two cycles Quarterly Bi-weekly Table C-1 FORM INES 205 2/80
C
I I
I NUCLEAR ENERGY SERVICES. INC.
DOCUMENT NO.
PAGE~OF~
System Valve Z.D.
Test 1
Req's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure Core Spray 81-01 81-02, B
81-21 B
81-22 B
ET ET ET, Stroke time=90 sec Stroke time=90 sec Stroke time=90 sec Stroke time=90 sec N1-ST-Q 1 N1-ST-Ql Nl-ST-Ql N1-ST-Ql 81A00 12 81A0012.
81A0012 81A0012 00-05 B
00-06 B
00-02'0-12 ET'T Stroke time=25 sec Stroke time=25 sec.
. Stroke time=25 sec Stroke time=25 sec Nl-ST-Ql Nl-ST-Ql Nl-ST-Ql N1-ST-Ql 81A0012.
81A0012 I
81A0012 I
81AOV12 00-01 00-09 B
Stroke time=25 sec Stroke time=25 sec Stroke time=25 sec Q
C Nl-ST-Ql Nl-ST-Ql' N1-ST-Ql C.
N1-ST-Q 1 N 1-ST-Ql Nl-ST-Ql 81A0012 81A0413
- 81A0412, 81A0013.
- 81A0012, 81A0013 00-11 B
ET PIT Stroke time=25 sec QC' 1-ST-'Q 1 Nl-ST-Ql 81A0012.,
81A0013 93-51 B
93-52 ET No stroke time limit No stroke time limit Nl-ST-Ql Nl-ST-Ql 81A0012 81A0412 1 LRT ET/p ET SRT PIT FST XT Leak. Rate Test Part-stroke Exercise Testing Full-stroke Exercise Testing Safety Relief Test Position Indicator Test Fail Safe Tes t Explosive Test 2 C Cyclic (every scheduled refueling outage) 2C'nce every two cycles Q
Quarterly Wb Bi-weekly Table C-1 FORM =.. NES 205 2/80
DOCUMENT No 81A0416 PAGE OF System Valve I.D.
C at ~
Test 1
Req's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure Core Spray 81-07 81-08 81-27 81-28 ET ET ET by NMFC by NMPC by NMPC by NMPC 81A0015 81A0015 81A0415 81A0415 CV-NC-11 NC-12 CV-126 127.
B B
ET ET Q
Q 81A0412
- 81A0012, 1 LRT ET/p ET SRT PIT FST XT Leak.,Rate Test Part-stroke Exercise Testing Pull-stroke Exercise Testing Safety Relief Test Position Indicator Test Fail Safe Test Explosive Test 2
C 2C Q
Cyclic (every scheduled refueling outage)
Once every two cycles Quarterly Bi-weekly Table C-1 FORM ONES 205 2j80
)
C
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO P
pAGE OF Sys t,em Valve I.D.
at.
Test.
1 Req's.
Test. Limits 2
Freq.
NMPC field test procedure
~'ES general procedure Containment Spray 93-09 93-10 93-11 93-12 ET ET by NMPC by NMPC by NMPC by NMPC 81A0015 8IA0015 81A00 1,5 81A0015'RT ET/p ET SRT PIT FST XT Leak Rate Test.
P art-stroke Exercise Testing Full-.stroke Exercise Testing Safety Relief Test Position Indicator Test Fail Safe Test Explosive Test 2
C 2C Q
Cyclic (every scheduled refueling outage)
Once every two cycles Quarterly Bi-weekly Table C-1 FORM -. NES 205 2/80
C
~ ',.
NUCLEAR ENERGY SERVICES, INC.
81A0416 DOCUMENT NO.
PAGE,C12 PF 20 System Valve T..D.
Test 1
R~q's.
Test Limits 2
Freqo NMPC field test procedure NES general procedure Core Spray 81-73 81-70 81-75 81-76 C
SRT C
SRT C
SRT C
SRT Setpoint=75 psig Setpoint=75 psig Setpoint=75 psig Setpoint=75 psig 2C by NMPC 2C by. NMPC 2C by NMPC 2C 'y NMPC 81A0015 81A0415 81A0015 81A0015 81.-11 81-31 C
Setpoint=320 psig 2C by NMPC 2C by NMPC 81A0415 81A0015 C
81-78 81-79 81-80 SRT'RT Setpoint=60 psig Setpoint=60 psig C
SRT Setpoint=60 psig Setpoint=60 psig 2C by NMPC 2C by NMPC 2C by NMPC 2C by NMPC 8IA0015 81A0015 81A0415 81A0015 LRT ET/p ET SRT PIT FST ZT Leak Rate Test Part-stroke Exercise Testing Eull-stroke Exercise Testing Safety Relief Test Position Tndicator. Test Fail Safe Test Explosive Test 2
C 2C Q
Cyclic (every scheduled refueling outage)
Once every two-cycles Quarterly Bi-weekly Table C-1 FORt/ = NES 205 2/80
C
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE~OF~
System Valve I.D.
Test 1
Rea's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure Containment Spray 80-01 80-02 80-21 80-22 ET ET Stroke time=70 sec Stroke time=70 sec Stroke time=70 sec Stroke time=70 sec N1-ST-Q5 N1-ST-Q5 Nl-ST-Q5 N1-ST-Q5 81A0412 81AOII12 81A0012 81A0012 80-15 80-16 80-35 80-36 ET ET Stroke time=60 sec.
Stroke time=60 sec Stroke time=60 sec Stroke time=60 sec Nl-ST-Q5 N1-ST-Q5 N1>>ST-'Q5 N1-ST-Q5 81A0012 81A0412 81A0412 81A0012 80-05 80-06 80-25 80-26 ET ET ET by NMPC by NMPC by NMPC by.NMPC 81A0015 81A0415 81A0015 81A0015 90-21 90-22 90-23 90-20 LRT ET/p ET SRT PI:
FST XT Leak Rate Test Part-stroke Exercise Testing Eull-stroke Exercise Testing Safety Relief Test Position Indicator Test, Fail Safe Test Explosive Test 2
C 2C Q
Cyclic (every scheduled-refueling outage)
Once every two cycles Quarterly Bi-sleekly Table C-1 FORM =.. tv'"S 205 2/80
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
S 0
PAGE~OF~
System Valve Z.D.
Test 1
Req's.
Test Limits 2
Freq.
NMPC field test procedure NES general procedure Containment Spray Raw Water 93-25 93-26 93-27 ET ET No stroke time limit No stroke time limit No stroke time limit Nl-ST-Q5 Nl-ST-Q5 Nl-ST-Q5 81A0012 81A0012 81A0012 93-28 ET No stroke time limit Nl-ST-Q5 81A0012.
FA E LRT ET/p ET SRT PIT FST XT Leak Rate Test Part-stroke Exercise Testing Full-stroke Exercise Testing Safety Relief Test Position,Indicator Test Fail Safe Test Explosive Test 2
C 2C Wb Cyclic (every scheduled refueling outage)
Once every two cycles Quarterly Bi-weekly Table C-1 FORM 8NES 205 2/80
NUCLEAR ENERGY SERVICES, INC.
DOCVIVIENTNO.
PAGg C15 PF
.20 System Valve I.D.
Test 1
Req's.
Test Limits 2
Freq.
%PC field test procedure HES general procedure:
Liquid Poison NP-05A 05B 00A 04B D
D XT XT SRT SRT Setpoint=1000 psig Setpoint=1000 psig C
C 2C 2C N1-MST-C2 N1-MST-C2 by NMPC by NMPC I
81A0010 81A0010 81A0015 8IA0015 39-01 39-02
~-
'I-60.1-14 15 16 17 00-03 00-13 by NMPC by NMPC 81A0415 81A0415.
02-19 02-20C'y NMPC by NMPC 81A0015 81A0015 1 LRT ET/p ET SRT PIT FST XT Leak Rate Test Part-s t roke Exercis e Tes ting Full-stroke Exercise Testing Safety Relief Test Position Indicator Test Pail Safe Test, Explosive Test 2 C Cyclic (every scheduled refueling outage) 2C Once every two cycles Q
Quarterly Vb Bi-sleekly Table C-1 FORM -.. NES 205 2/80
~ 78II 44j'
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO..
PAGE~OF~
Frequency C Field rocedure System Valve Number Tes t Requirements
.Quarterly N1-ST-Q0 Cleanup 33-01 33-02 33-00 Exercising Test'mergency Condenser N1-ST-Ql Core Spray 39-09 39-10 39-07 39-08 CV-NC-11 NC-12 39-11 39-12 39-13 39-10 81-01 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 Exercising Test, Fail-Safe Test Exercising Test TABLEC-2 FORM ~ NES 205 2/80
~'
NUCLEAR ENERGY SERYICES, INC.
DOCUMENT NO.
l PAGE~GP~
Frequency C Field rocedure
'System Valve Number Tes r.
Requirem'ends Quarteriy (Cont'd)
N1-ST<<Q5 Nl-ST-M2 by NMPC Contairiment Spray Containment Spray Raw Water Emerg. Cond Make Up Core Spray Containment Spray Liquid Poison Emer. Service Water 80-01 80-02 80-21 80-22 80-15 S0-16
&0-35 80-36 93-25 93-26 93-27 93-28 93-09 93-10 93-11 93-12 60-17 60-18 81-07 81-08 81-27 81-28 80-05 80-06 80-25 80-26 02-19 II2-20 72-66 72-77 72-78 72-79 68-01 68-02 68-03 68-00 Exercising Test P
1'ABLE C-2 FORM =.. NES 205 2/80
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PaGE~OP~
Frequency C Field rocedure System Valve Number Yes t Requirem'erits Bi-vIeekly N1-ST-V4 Main Steam 01-01 01-02 01-03 01-04 part stroke Exercising Test Feedwater 31-03 31-00 TABLE C-2 FORtd =,N=S 205 2/80
NUCLEAR ENERGY SERVICES. INC.
~
~
~
DOCUMENT NO.
S O4 e
p~sa ~or-
~0 Frequency Every 2 cycles C Field rocedure by NMPC Main Steam Valve Number N?A N7B N7C N7D N7E N7F N?G.
N?H N?3 N7K N7M N7N N?U N7R N7S N7T Tes t Requirem'ents Safety Relief Test Core Spray Liquid Poison
~
81-73 81-70 81-75 81-76 81-11, 81-31 81-77 81-78 81-?9 81-80 NPOOA NPOWB
~ 4 a
4 TABLEC-2 FORM% N'ES 205 2/SO
NUCLEAR ENERGY SERVICES, INC.
E DOCUMENT NO, 81A0416 PAGE~2pP Ep Frequency C Field rocedure System Valve Number Yes t Requirements Cyclic N1-ISP-25.1 Main Steam 01-01 01-02 01.-03 01-00 Leak Rate Test N1-ST-C2 Nl-ST-R8 NR-108 A thru F 01-01 01-02 Safety Relief Test Exercising Test, Position Indicating
- Test, C
Feedwater Shutdown Cooling Nl<<MST-C2 'iquid Poison 01-03 01-00 31-03 31-00 38-01 38-13 38-02 NP05A NP05B Exercising Test, Fail-Safe Exercising Test, Position Indicating Test Exercising Test'xplosive Test N1-ST-Q4 Cleanup 33-01 33-02 Position Indicating Test Nl-ST-Ql Emergency Condenser Core Spray 39-05 39-06 00-01 00-09 00-10 40-11 Exercising Test, Fail-Safe
~
I Position Indicating Test TABLEC-2 FORM% NES 205 2/80
gf/
NUCLEAR ENERGY SERVlCES, INC.
E DOCUMENT NO.
PAGE O>
OF APPENDIX D GENERAL TEST PROCEDURES
~
~ ~
FORM-NES 205 2/80
t II NUCLEAR ENERGY SERVICES, INC.
DOCuMENT NO
'83A0416 PAGE OF 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
'nform 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
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
8~04'~
PAGE Ei OF APPENDIX E RECORDS FORM -"NES 205 2/80
C
NUCLEAR ENERGY SERViCES, INC.
DOCUMENT NO.
81A0416 E2
=2 PAGE OF 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
Figure 2 Figure 3 Figure 0 Figure 5 Figure 6 Figure 7 Figure 8
,Figure 9 Figure 10 Pump Summary Sheet Pump Data Sheet Pump Reference Data Sheet
'ump Analysis Sheet Valve Summary Sheet Valve Leak Rate Test Sheet Exercising Test Data Sheet Valve Position Indicator Test Data Sheet
....'ategory D Explosively Activated Valve Test Sheet 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 Manufacturer System Page Model Serial No.
Field Test Proc.
No.
Test.
No.
Test'ate Accep.
Range Alert Range Test Successful Req'd Action Range Comments Ref.
Data Set No.
FIGURE 1
" "Q NVMEAQENECIQV SK41~CTS le@
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RRSL LLEW ewmm SLSL
~ 0 0
~
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ASHE SECTION XI INSLRVICE TESTING VALVE
SUMMARY
SHEET Valve I D System Size Manufacturer Field Test Proc.
No./Rev.
TYpe Category Hodel Page Test No.
1 Date Pass Fai 1
Rema rks.
(>)
LR-ET PIT SRT XT Leak Rate Test Exercising Test Position Indicator Test Safety Relief Test Explosive Test Fig.
5 9 tlvCLEAHEHE'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 t No LRT-.
Manufacturer Date Model Field Test Proc.
No./Rev.
PART I Leaka e Measurement Test DP psi Nedium Temp. '.
ml/h (water) scfd (a i r) v Permissible ml/h (wa te r)
Measured Leak Rate:
scfd (air) ',
Leak Rate:
If Valve(6", go to
SUMMARY
If Valve>6", complete Parts 2 and 3.
PART 2 Margin Calculation MR" LR MR -
PR NR Maximum Permissible Leak Rate 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)
Fig.
6 (over) sf'UCLEAR 'ENERGY SEA'ACES lNC
/J
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 Valve
>6" only PART 1
Leakage Measurement PART 2 Margin Caicuiation PART 3
Projection Caicuiation lf 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 Person(s}
responsible for Test Date 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 System Size Type Manufacturer Category Model Test No.
PART 1
Stroke Test Date Fiel d Test.
(from Field Test Proc.
No./Rev.
Procedure)
Part-stroke test Full-stroke test Test successful 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 Limiting Value of Stroke Time sec iieasured stroke time shorter than or'qual to 1 imiting time (Pass) iieasured stroke time longer than limiting time (Fail) ii.
Increase in Stroke Time Measured stroke time (this test)
Measured stroke time (previous) sec 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 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
?
Fig.7
': Yes No (over) r.Q NUCLEAAENRAGY SEPAL c5.1!Sm
~
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C
ASHE SECTION XI'NSERVICE TESTING CATEGORY D EXPLOSIVELY ACTUATED VALVE TEST (XT)
DATA SHEET Valve ID SYstem Size Hanufactu'rer TYPe Mode1 XT-
, Test No.
Test Date (from fiel d test procedure)
Field Test Proc.
No./Rev.
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 Person(s) responsible for Test Date Fig.
9 p
C O'Li 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 Test. No.
Manufacturer Test Date Model 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 Person(s) responsible for Test Date Fig. 1O 0
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NUCLEAR ENERGY SERVlCES, lNC.
DOCUMENT NO, 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 N1-ST-Q6 Nl-ST-Q2 Nl-ST-M 1 Core Spray Pumps and Motor Operated Valves Operabiity Test Containment Spray and Raw Water Pumps Operability Test Control Rod Drive Pumps Flow Rate Test Liquid Poison Pump Flow Rate Discharge Pressure Test Nl-ST-M0 Nl-ST-QO Nl-ST-Rs N1-ST-Q5 N 1-MST-C2 Nl-ST-V0 Emergency Diesel G.enerators Manual Start and One Hour Rated Load Test Reactor Coolant System Isolation Valves Exercising Test Reactor Coolant and Piimary Containment Isolation Valves and Timing Primary Containment isolation Valves Exercising Liquid Poison Squib Valves Test Firing and Inspection Feedwater and Main Steam Line Power Operated Isolated Isolation Valves Exercise Test N1-ST-C2 Manual Opening of the Solenoid-Actuated Pressure Relief Valves and Flow. Verification NI-ISP-25.1 N 1-ST-M 2 Main Steam Isolation Valves Leak Rate Tests Emergency Cooling System Makeup Tank Level Control Valves Exercise Tests FORM - NES 205 2/80
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