ML20204G582
| ML20204G582 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/26/1988 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20204G580 | List: |
| References | |
| PROC-880926, NUDOCS 8810240157 | |
| Download: ML20204G582 (176) | |
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CALVERT CLIFFS NUCLEAR POWER PLANT BALTIMORE GAS & ELECTRIC LOMPANY ASME SECTION XI PUMP AND VALVE TEST PROGRAMS - UNITS 1 Aht 2 SECOND TEN-YEAR INIT.RVAL i
Rev. 1 9/26/88 0810240157 esgogg yDR ADOCK 050003g7 PDC
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. TABLE OF CONTENTS PAGE TITM SECTION 1
1.0 INTRODUCTIOh.....................
1 1.1 Relationship with Technical Specifications 1
1.2 Qualification of Test Personnel.
1 2.0 PUMP INSERVICE TEST PROGRAM 2
2.1 Pump Bearing Temperature / Vibration Measurement 2
2.2 Pump Testing Ranges.
2 2.3 Emergency Diesel Systems 3
2.4 Hultiple Reference Values.
3 VALVE INSERVICE TEST PROGRAM..
3.0 3
3.1. Category A Valves.
4 3.2 Pressure Isolation Valves.
5 3.3 Thermal Relief Valves.
5 3.4 Cold Shutdown Testing.
5 3.5 Part-Stroke Testing.
6 3.6 Fail-Safe Actuators.
6 3.7 Valve Timing and Remote Indication 6
3.8 Passive Valves 6
3.9 Stroke Times 7
3.10 Shut Down Cooling Valves 7
3.11 Post-Maintenance Testing 7
3.12 Relief Valve Testing REFERENCES UNITS 1 AND 2 PUMP TESTING PROGRAM APPENDIX A LEGEND FOR VALVE TESTING PROGRAM APPENDIX !
APPENDIX C UNIT 1 VALVE TESTING PROGRAM UNIT 2 VALVE TESTING PROGRAM APPENDIX D VALVES TESTED DURING COLD SR'JTDOWN APPENDIX E APPENDIX F DRAWINGS USED IN PREPARATION APPENDIX G PREVIOUS TEST PROGRAMS DOCUMENTATION AND Crix0NOLOGY OP SUBMITTALS APPENDIX 11 Rev. 1 1
9/26/88
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INSERVICE 'ITSTING PROGRAM FOR PUMPS AND VALVES
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CALVERT CLIFFS NUCLEAR POWER PLANT
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UNITS 1 AND 2 1.0 IN!1000CTION l
d pumps
- Under the provisions of 10CFR50.55a, inservice testing of safety re ate and valves will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable ' Addenda.
As specified in
-10CFR50.55a(b), the ef fect ive edition of Section XI witn ragard to this t
program is the 1983 Edition through the Summer 1983 ; Addenda.
This program identifies the pump and valve inservice testing'that will be performed at the Calvert Cliffs Nuclear Power Plant Unita 1 and 2 to comply with the of 10CFR50.55a.
This program applies to.the Seco.7d Ten Year requirements Inservice Inspection Interval beginning April 1, 1987.
1.1 Relationship with Technical SpecificatigrLs The ASME Section XI Pump and Valve Test Program is required by Calvert Cliffs Nuclear Power Plant Technical Specification 4.0.5 as Based on Technical Specification requirements, in well as 10CFR50.
the event of any conflicts between ASME Section XI requirements and the requirements of Technical Spec.ifications, the ' plant. Technical Since Calvert Cliffs may be updating Specifications shall govern.its Refuelina Cycle to 24 months, ASME Sectio to the time interval of 2 years, will be tested during each refueling.
1.2 Qualification of Test. Personnel Personnel performing pump and valve testing per ASME Section XI Subsections IWP and IWV will be qualified in accordance with the This is in keeping with Calvert Cliffs Quality Assurance Program.
the requirements of ASME Section XI, as clarified by ASME Code Interpretation XI-1-82-06R.
f' 2.0 PUMP IN5gRVICE '!1 STING._ PROGRAM f
program shall be conducted in accordance with Subsection The pump test 1983 Edition of the ASME Boiler and Prepoure IWP of Section XI of the Vessel Code through Suonner 1983 Addenda, except for relief requested l
Appendix A details the l
under the provisions of 10CFR50.55a(g) (5) (111).
inservice testing program for all safety related pumps at Calvert Clif fs These tables list each pump required l
Nuclear Power Plant Units 1 and 2.
Each 3
to be tested in accordance with IWP-1100 of Section XT of the Code.
l parnmeter to be measured, as well as specific relief requests coneArning non-conformance, are also listed.
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Pump Bearing Temperature / Vibration Measurement 2.1 L
Subsection IWP-3300 requires pump bearing temperatures be measured
[.
Industry experience demonstrates that at least once each year.
typically rise only minutes prior to failure.
bearing temperatures Any bearing failure predicted by a yearly recording of bearing f
temperature would be a random event and thus, yearly measurement of bearing temperatures does not increase the level of confidence in component reliability. The expense of adding the additional testing therefore, l
both in component degradation and man-hours expended is, not justified.
Further, IWP-3500(b) specifies that pumps be run until bearing temperatures stabilize as determined by three measurements at 10 minute intervals.
Clearly the pump would have to '-
run in excess of one-half hour to obtain these readings.
The nump degradation caused by this requirement does not justify the very limited assurance it might provide.
least a quarterly basis will be used to Vibration data taken on at This request for relief should define pump mechanical condition.
apply for all bearings presently required to be temperature tested.
2.2 Pump Testing Ranzes and Action Clif fs will revise the upper boundary for Alert Calvert and flow for selected punps.
This ranges of dif ferential pressure position reflects the approved relief request from the first ten year program and meets with ASME Code Requiremeats per 1WP-3210.
Pump performance will be adequately evaluated using upper limits of 1.05 and 1.07 (times dif ferential pressure or flow range appropriate) for the Alert and Action delte P/ flow reference, as rangos respectively.
Normal operation of the pumps in these ranges As identified in will still meet their required safety function.
the first ten year testing program NRC safety evaluation, "Smell positive increases in observed delta P are most likelv not significant with regard to centrifugal pumps.
More over, such instrument uncertainty, water density, and instrument lead to spurious actuation of alert and action ranges."
factors as error might Based on the above, these reduced range limits are felt to meet the intent and requirements of ASME Section XI.
2.3 Emergency Diesel Systems The inservice operability testing of pumps (and valves) associated with the Emergency Diesels, including the Diesel Oil Transfer These System, are excluded from the enclosed test programs.
components are considered an integral part of the Emergency Diesel System and are functionally tested at least monthly per Technical Specifications.
Thus, the functional eperability testing of the pumps and valves is performed at a frequency greater than that required by Section XI for either pumps or valves.
Additionally, the failure of a pump or valve to perform its intended function will be identified by the failure of the associated Emergency Diesel to Rev. 1 2
9/26/88
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meet its functional requirements.
Calvert Cliffs Technical Specifications and plant maintenance schedules together provide assurance of operability aa well as information concerning equipment degradation over tine.
f 2.4 Hultiple Reference Values Based on plant operating conditions and - pump testing hydrau2!.c-Calvert Cliffs may choose to generate multiple sets of
- circuit, reference values (per IWP-3112) in order to more fully descr %e pum, hydraulic condition.
Each set of rump reference values ~ will mee:
all appropriate requirements of IWP-3000.
3.0 VALVE INSERVICE 11LSTING PROGRAM The valve test program for Calvert Clif fs Nuclear Power Plant Units 1 and 2 shall be conducted in accordance with Subsection IWV of Section XI of 1983 Edition of the ASME Boller and Pressare Vessel Code through the the Summer 1983 Addenda, except for relief requested under the provisions of 10CTR50.55a(g) (5) (111).
The valve test program for Unit 1 is included as Appendix C, and Unit 2 is included as Appendix D.
The codes and symbols used to abbreviate the tables in Appendices C and D are explained in Appendix B.
3.1 Cates,ory A Valves Valve for which seat leakage x
'.mportant may generally be classified as pressure isolation valves (PSIV), containment isolation valves (CIV),
or both pressure
.nd containment isolation valves.
isolation valves falling within the scope of ASME Containment Section XI are tested in accordance with the Section XI requirements of IWV-3410, Category A, with the exception of the seat leakage tests (IWV-3420).
The seat leakage testing performed on these valves meets the intent of Section XI, but the actual test procedures shall be conducted in accordance with the 10CFR50, Appendix J.
Type C, CIV test program.
For valves performing a containment isolation function, individual valve leak rates are not in themselves significant.
The only pertinent leak rate criteria for CIV's is that the total leak rate for all penetrations and valves be less than 0.60 L, The Calvert Cliffs Nuclear Power Plant 1 and 2 were designe$ to perform the Appendix J. Type C cests, Units not the individual Category A leak test (i.e., some penetration test connections test more than one valve at a time).
Accordingly, all leak testing shall be performed in accordance with the CIV seat requirements of 10CTR50, Appendix J. Type C, in lieu of the Category A requirements of Section XI.
and will, All CIVs have been categorized as A-Active or A-Passive, as a minimum, be leak tested per 10CFR50, Appendix J.
Passive valves will in ger.wral have no other testing performed.
Valves 1 CVC-103 and 1-CVC 105 in the Reactor Coolant Letdown Line (P6ID a leak test 0;l-73) have been analyzed as passively open, however, will be performed per Appendix J at refueling intervals.
Valves also leak tested, even though the valves 1-CV 518 and 1-CV-519 are A similar sitvation exists on Unit 2.
fail open upon loss of power.
Rev. 1 3
9/26/88
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3.2 Pressure Isolation Valves The purpose of the Pressure dystem Isolation Valves (PSIV's) is to reduce the possibility of an inter-system L6CA which would pressurize low pressure systems to pressures exceeding their design limits.
At Calvert Cliffs Nuclear Power Plant Units 1 and 2, the following PSIV's are leak tested:
SI-118 (11A (21B) SI header check)
SI-128 (lib (21A) SI header check)
SI-138 (12A (228) SI header check)
SI-148 (12B (22A) SI header check)
SI-217 (11A (218) loop inlet check)
SI-227 (11B (21A) loop inlet check)51-237 (12A (22B) loop inlet check)
SI-247 (12B (22A) loop inlet check)
SI-215 (11A (21B) SI tank outlet check)
SI-225 (11B (21A) SI tank outlet check)
SI-235 (12A (22B) SI tank outist check)
SI-245 (12B (22A) SI tank outlet check)
Valves SI-118, SI-128, SI-138, and SI-148 isolate the Safety Injection Headers (LPSI and HPSI) from the Safety Injection Tank These valves are individually leak tested in accordance discharges.
with IWV-3420.
For the loop inlet check valves, there is a pressure indicator that alarms on high pressure between adjacent loop inlet and tank cutlet Using this it.dication, it is valves displayed in the control room.
possible to determine the pressure between the valves (for example, SI-215 and SI-217).
Thus, should reactor coolant loop inlet check valve SI-217 f ail, the pressure increase betusen SI-217 and SI-215 would be noted in the control room.
Procedures require the operator take positive measures to assess check valve leakage following recalpt of an alarm. See also Relief Request SI 4.
For the tank outlet valves, these valves are leak tested by pressurizing the dowr.Etream side of the valve and then determining the valve leakage by noting the change in SI Tank level.
Calvert Cliffs feels that these testo meet the intent of leak testing per IWV-3420, and the above positions were approved by the NRC during the first ten year pump and valve program.
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3.3 Thermal Relief Valves exchangers, Many safety related system, particularly those with heat have been provided with relief valves.
These relief valves are thermal relief valves (TRV) of small capacity intended to relieve "bott12d-up" pressure due to thermal expansion of fluid in a condition.
Experience has shown that failure of these valves will not result in failure of a system to fulfill its safety related thermal relief valves are not considered to perform function.
- Thus, a function important to safety and such valves have not been included in the program.
3.4 Cold Shutdown Testing f requency in Appendices C and D is specified as "C" Where the test (Cold Shutdown) the following definition for cold shutdown testing applies:
For unplanned or forced outages, testing uill commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> aftar cold shutdown (Mode 5) is achieved.
prerequisite to Completion of all valve testing is not a subsequent startup.
Any testing not completed at one cold shutdown will be perforced during subsequent cold shutdowns (excluding refuelings) tv meet ss close as practical the planned outages 6
specified Section XI testing frequency.
where all required testing can be completec tception to the above start time may be taken.
- However, a.
esting must be completed consistent with Section XI requi. ients prior to startup.
Appendix E specifically identifies those valves tested during Cold for each.
Valves tested Shutdowns, with operational justifications on a Cold Shutdown frequency may be tested in Modes 2, 3, 4, or 5 as 9propriate for each specific valve (i.e., some valves may be tested during outage recovery, etc.).
3.5 Eart Stroke Test _in; The goal of the Calvert Cliffs Inservice Program for valves is to perform full-stroke tests of all appropriate valves.
With the exception of those valves for which specific rel-n Enen requested, all valves will be full stroke tested whene er & ( ie.
Part stroke testing of power-operated valves is genere ty not possible, due to velve logic circuitry which only allows full-open
'ull-closed valve movement.
Moreover, the intent of Section XI is to assess valve operability through inservice testing; while a or part-stroke exercise does provide some measure of confidence in valva operability, it does not provide assurance of valve safety related function.
In
- addition, a
part-stroke of a
valve has the possibility, throvvh human or power operatedmechanical error, to cause adverse plant consequences (isolation of cooling water, plant transients, etc.)
via an inadvertent full-stroke.
Based on the above, Calvert Cliffs will full-stroke Rev. 1 5
9/16/88
i test power-operated valves in accordance with the Valve Test Program (with associated relief requests as appropriate).
Check valves whose safety function is to open will be full-stroked when possible.
Since disk position is not e1 ways observable, the NRC staff has stated that "verification" of the plant's safety an aly,.is flow rate through the check valve woulc' be an adequate demonstration of full stroke requirement.
Any flow rate less than design will be considered part-stroke exarcising unless it can be shown that the check valve s disk position at the lower flow rate would be equivalent to or greater than the design flow rate through the valve.'
Based on this position, check valves within the scope of this test program will be at least part-stroke exercised whenever any flow in passed strough the valve.
Check valves are considered to be full-stroke tested on at least the Code-required frequency, unless identified by Relief Request.
Check valves for which a full-stroke exe cise can not be confirmed, therefore, will be
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identified by n appropriate relief request.
Calvert Cliffs feels
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that this pt.t at ion me ts the intent of IVV-3522(b) regarding exercising of check valves.
3.6 Tail-Safe Actuators All those velins wh.ch have a fail-safe actuator are erarcised normally using that actuator.
- hus, the fail-safe aest.or ir regultrly tested when the vah 4 is tested.
3.7 Va.1ve_ Position Indientor Verification Verification of valve pos! tion indicator accuracy will be performed in accordance with Section XI IVV-3300.
The verification of the valve position of solenoid operated valves may be done by observation of appropriate system parameter such as pressure or flow changes.
L3 Eassive Valves Tnese
- valves, which have no Section XI operability testing requirements, are valves in safety-related system which are not required to change position in order to accomplish their required as passive safety-function.
Calvert Cliffs has categorized valves which are administratively locked open et locked-closed in their saf ety-related position.
Due to the lack of testing requirements, B-Passive valves have been excluded from Appendices C and D.
3.9 Stroke __ Times The valvt stroke #>
eatifin Appendices C and D may change due to modificatiot "tensnce, ver plant lifetime.
Calvert as necessary, incorporating Cliffs will c:.anyc the requirements - A
'chout further notification.
Fev. 1 6
9/26/88 q
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3.10 Shutdown Cooling Valves function will Power-opet ated valves used for Shutdown Cooling (SDC)
Manual valves in the be tested in accordas.ce with ASME Section XI.Slian the systems for SDC system that require a position change to operation are considered to be functionally tested whenever SDC is in use (at least during each Cold Shutdown).
Based on this functional test, these manual valve have been excluded from the associated Valve Test Program Tables.
3.11 Lost-Maintenance Testing be tested during tested on a Cold Shutdown f requency cannot Valves power operation due to system limitations, persornel safety, etc.
Therefore, for minor maintenance on such valves during power operation which does not remove the valve from service, valve post-maintenance testing will be performed at the earliest available opportunity, i.e., in Cold Shutdown.
3.12 Relief Valve 'Lesting Calvert Cliffs will perform all Relief Valve Testing using POSRC-approved procedures under the requirements of the Technical Specification Surseillance Testing Program.
This level ra f administrative control, including the requirement 9 for Quality Assurance / Control per 10CFR50 Appendix B, ensures the overall test quality is maintained.
Therefore, Calvert Cliffs feels that the intent of PTC-25.3 for relief valve testing regarding test personnel and test group makeup, are met.
In addition, the qualificationspersonnel are trained and qualified in accordance with Calvert test for Surveillance Test Personnel.
Cliffs Administrative Requirements Therefore, the requirement of PTC 25.3 to have the test witnessed is not necessary.
However, all test results by a degreed engineer reviewed by appropriate supervisory and of relief valve testing ere See Relief Request engineerir.g personnel prior to test acceptance.
A-3 for Units 1 & 2.
Rev. 1 7
9/26/88
j REFERENCES f
1983 ASME Boiler and Preesure 1983 Edition with Addenda throu gh Summer Section XI:
Ru.ts for Inservice Inspection of Nuclear o
f Vessel Code Power Plant Components o
Calvert Clif f s Nuclear Power Plant Units 1& 2; Piping and Instrument Diagrams Calvert Cliffs Nuclear Power Plant Units 1 & 2; Operations Drawings (see o
Appendix F)
Calvert Cliffs Nuclear Power Plant Units 1 & 2; Technical Specifications o
ASME o
CCI-104H, Appendix 104.60 Attachment (4), Pages 1 through 28 Section XI Pump and Valve List STP-M-571-1 (Revision 6) of LLRT 1, Pages 1 through 13 o
OTP-M-571-2 (Revision 13) of LLRT-1 Pages 218 through 230 o
o Unit 1 Pump and Valve Inservice Test Program, 1st Ten Year Interval (see Appendix G)
Unit 2 Pump and Valve Inservice Test Progrcm, 1st Ten Year Interval (see o
Appendix G)
M-601 (Propose / Revision 26) Pipinc Class Summary Sheets - March 3, 1986 o
Calvert Cliffs Nuclear Power Plant Units 1 & 2; Inservice Inspection and and Valve Programs Request for Roller f rora ASME Code Section XI o
Pump 1982 (see Appendix Requirements Determined to be Impractical - August 30, 11 )
December 22, 1982 (ses Saf oty Evaluation and Federal Register Notice o
Appendix H)
Safety Evaluation Granting Relief From ASME Code Section XI Inservice o
Testing Requirements - February t, 1982 (see Appendix H)
Rev. 1 Ref. 1-1 9/26/88
APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLAST UNITS 1 AND 2 PUMP INSERVICE TESTING PROGRAM 4
Rev. 1 9/26/88
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1 APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 PUMP INSERVICE TESTIiiG PROGRAM l
Fuammary of_Informatfon Provided The pump test table provides the following information on testing requirements:
o Pump Name/No.
o ASME Class Drawing on which the pump is depicted o
o Inlet Pressure Differential Pressure o
o Flow Rate Vibration Amplitude o
Observation of Lube Oil Level o
o Bearing Temperature o
Speed Specific Reliet' Requests are identified as notes in the Tables, and is immediately folltv each Unit's Table.
Test f requency for all parameters identified oy a "Q" for Quarterly, unless revised by Felief Request.
4 Re".
1 A-1 9/26/88
CALVERT CLIFFS NUCIIAR PChT.R PIANT - LNIT 1 REQUIRED PLMP Tr.STS P&ID Bearing Pump Name/ Number Class (OM-) Pressure Pressure Flowrate. Vibration Lubricant Temparature Speed" Remarks ASME No.
Inlet Differential F
liigh Pressure SI/11 2
74 Q
Q Q
Q 3
NA RR6 iligh Pressure SI/12 2
74 Q
Q 7
Q Q
3 NA RR6 High Pressure SI/13 2
74 Q
Q 7
Q Q
3 NA RR6 Im Pressure F '/11 2
74 Q
Q 7
Q Q
j NA RR6 Low Pressure Sh'12 2
74 Q
Q 7
Q Q
3 NA RR6 Conta'uuent Spray /11 2
74 Q
Q 7
Q Q
3 NA RR6 Containment Spray /12 2
74 Q
Q 7
Q Q
3 NA RR6 Boric Acid /11 2
73 Q
Q Q
Q Q
3 NA RR6 Boric Acid /12 2
73 Q
Q Q
Q Q
3 NA RR6 Charging /11 2
73 4
5 Q
Q Q
3 NA RR6 Reactor Coolant Charging /12 2
73 4
5 Q
Q Q
3 NA RR6 E actor Coolant Charging /13 2
73 4
5 Q
Q Q
3 NA RR6 Reactor Coolant e - Other than those identified for testing, all pumps are s c.chronous/ induction wound moters l
Rev. I A-2 9/26/88
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6 6
6 6
6 6
6 6
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R R
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R R
R R
R R
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A A
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A A
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N N
N N
N N
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3 3
3 3
3 3
3 3
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Unit 1 REI.IEF REQUEST NUMBER 1 i
System:
Circulating Salt Water Cooling P&ID:
OH-49 Pumps:
Salt Water Pumps Nor,, 11, 12, and 13 Class:
3 inlet IVP-3100 requirement to measure Impractical Test Requireennt:
pressure befc,re startup and during test.
Basis for Relief:
Salt water pump suction pressure taps do not exist. The pumps take suction directly from the intake bay through two redundant suction canals.
Pump suction is situated feet below Chesapeake Bay mean low water level; seven therefore, pump suction is a function of bay water level.
Chesapeake Bay mean level is not considered to change during test performance.
Bay water level 4.s recorded once during the test and Alternativo Testing:
used to compute pump suction pressure.
Rev. 1 A-4 9/26/88
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Unit I l
RELIEF REQUEST NUMBER 2 Circulating Salt Water Cooling and Component Cooling Water System:
P&ID:
OM-49 and OM-51 Pumps:
Salt Water Pumps Nos. 11, 12, and 13 and Component Cooling Vater Pumps Nos. 11, 12, and 13 j
f Classt 3
IWP-3100 requirement to observe proper Impractical Test Requirement:
lubrica.nt level or pressure.
The salt water pumps and compot.ent cooling pumps have Basis. for Relief:
grease lubricated bearings.
Therefore, observation of lubricant level or pressure is not appropriate.
The bearings are greased in accordance with Alternative Testing:
None.
the manufacturer's ir.at ruct ions on a
regular preventative maintenance schedule.
Rev. 1 A-5 9/26/88
Unit 1 l
I t
RELIEF REQUEST NLMBER 3 i
Chemical and Volume Control (L th Charging a.nd Boric Acid), Low Pressure Safety
- Injectkn, High Pressure Safety Injection, Systems:
Cont ainr.ent Spray, Salt Water Cooling, Component Cooling, Auxiliary Feedwates, Lervice Water PtilD's :
Various Pumps:
All Safety Related Pumps Class:
2/3 IVP-3100 requirement to measure bearing Impractical Teat Requirement:
temperature, and IVP-3000 requirements to measure vibration amplitude.
The referenced code requires bearing temperature to be Basin for Relief:
It has been demonstrated by experience recorded annually.
that bearing temperature rise occurs only minutes prior to bearing failure.
Therefore, the detection of possible bearing failure by a yearly temperature measurement is ertremely unlikely.
It requires at least one half hour of pump operation to achieve stable bearing temperatures.
The small probability of detecting bearing t'ailur e by temperature measurement does not justify the additional pump operating time required to obtain the measurements.
As an alternative, the pump vibration testing will be expanded f rom one to multiple readings in two orthogonal directions.
These pumps are part of the Calvert Cliffs Vibration Testing Program, and as such, are tested at least on a quarterly basis utilizing a vibration analysis system.
The results of this rigorous analysis provide much more definite information regarding pump mechanical condition than do bearing temperature measurements.
Based upon this, CCNPP does not require annual bearing temperature measurements per the ASME Jection XI Code in order to assess pump mechanical condition.
<ill be Alternative Testing:
Results of the regular vibration evaluet!'n least utilized to assess pump mechanical condition at quarterly.
Results of this calculation will be maintained as a part of the Pump Record.
Res. 1 A-6 9/26/88
Unit 1 RELIEF REQUEST NUMBER 4 Chemical and Volume Control System:
P&ID:
OM-73 Reactor Coolant Charging Pumps Nos. 11, 12, and 13 Pumps:
Class:
2 1WP-3100 requirement to measure pump Impractical Test Requircaent:
suction pressure.
The reactor coolant charging pumps normally take their Basis for Relief:
suction from the outlet of the volume control tank.
The volume control tank is equipped with an automatic make-up g
um
+ystem to prevent low level operation.
If volume control a low level alarm is provided
.ank level should decrease, to alert the operator to the need for corrective action.
If volume control tank level continues to decrease, a low-low level alarm is actuated and charging pump suction is automatically shifted to the refueling water tank.
the charging pumps be starved for flow as the Should result of a piping rupture or inadvertent valvo closure, a
decreasing flow rate would be observed and the pump would trip on low suction pressure.
Alternative Testing:
None. The system design discussed above provides adequate indication of and protection from a low suction pressure conditiv.n.
Rev. 1 A-7 9/26/88
1 Unit 1 RELIEF REQUEST NUKBER 5 Chemical and Volume Control System:
P&lD:
OM-73 Reactor Coolant Charging Pumps Nos. 11, 12, and 13 Pumps:
Class:
2 IWP-3100 requirement to measure pump Impractical Test Requirement:
differential pressure.
Basis for Relief:
Due to pump design, the pump differential pressure is not indicative of pump performance.
Positive displacement pump dif ferentici pressure varies across a wide spectrum, based on system conditions, without a change in flowrate.
Pump flowrate will be measured and used tc, assess Alternative Testing:
pump hydraulic condition in lieu of pump differencial pressure.
Rev. 1 A-8 9/26/88
l I
Urdt 1 RELIF3 REQUEST NUMBER 6 System:
As Required, Unit 1 pfilD:
Where Applicable Ansps:
As Required
)
Table IWP-4110-1 requires the instrument Impractical Test Requirement: accuracy of the flow instrument used in testing to be i 2% of full scale.
i Many of the pumps within the scope of IWP are tested by Basis for Relief:
using ultrascnic or annubar flow meters.
Due to the timeframe of construction for CCNPP, specific test flow monitoring equipment was not part of the original fesign To install instrumentation meeting the requirement basis.
of Table IVP-4110-1 would require extensive piping In addition, to improve re-configuration of most systems, in extreme the accuracy of existing methods would result for continuous vendor or national labs expense Current re-calibration of instruments between every test.
exr>erience with the existing instrumen+.ation provides confidence that the proposed accuracy will be adequate to determine if a pump is degrading.
All flow messuring instruments will meet a loop Alternative Requiromants:
accuracy of i 4*.
of full scale accuracy.
The repeatability of the instruments will be within the requirement of Table IWP-4110-1.
Rev. 1 A-9 1
Sf 26/88
l l
thit 1 RELIEF REQUEST NUMBER 7 Auxiliary Feedwater (AW)/lligh Prnssure Safety Injection (HPSI)/ Low Systems:
Pressure Safety Injection (LPSI)/ Containment Sprey (CS).
P61Ds:
M-800/74 i
Pumps:
AW; 11, 12, and 13
!! PSI; 11, 12, and 13 LPSI; 11 and 12 CS; 11 and 12 Class:
2 and 3 Table IWP 3100-2 requires that flow be monitored lepractical Test Requirement: and maintained within a set allowabla range, t
These pumps are tested in a mini-recirculation flow loop Basis for Relief:
due to the impracticability of full flow testing during power operation.
The AW, llPSI, LPSI, and CS Pumps, if full flow tested, would result in thermal shock to equipment nozzles or deluge of equipment in containment with borated water.
A recirculation loop provides a
relatively fixed resistance flow path.
Tank level does not have a significant impact on recirculatisa flow for a relatively any of these pumps.
Each of the pumps has flat hydraulic characteristic curve within the flow range.
Monitoring flow and checking recirculation against an allowable vange provides no meaningful input to pump performance.
Quarterly testing will be performed without Alternative Testing:
evaluating flow.
At each refueling outage a large flow test will be conducted with flowrate being evaluated along with all otier pump vibration and hydraulic performance indicators.
Rev. 1 A-10 9/26/88
- - ~ _
CALVERT CLIFFS NUCIIAR P(L'ER PLANT - UNIT 2 REQUIRED PUMP TESTS P&ID Eearing ASME No.
Inlet Differential Speed" Remarks Pump Name/ Number Class (OM-) Pressure Pressure Flowrate Vibration Lubricant Temperature 3
NA RR-6 gh Pressure SI/21 2
462 Q
Q 7
Q Q
liigh Pressure 51/22 2
462 Q
Q 7
Q Q
3 NA RR-6 High Pressure SI/23 2
462 Q
Q 7
Q Q
3 NA RL-6 Im Pressure S1/21 2
462 Q
Q 7
Q Q
3 NA RR-6 i
l Im Pressure 51/22 2
462 Q
Q 7
Q Q
3 NA RR-6 Containment Sprey/21 2
462 Q
Q 7
Q Q
3 NA RR-6 Containment Spray /22 2
462 Q
Q 7
Q Q
3 NA RR-6 Boric 1.cid/21 2
461 Q
Q Q
Q Q
3 NA RR-6
~
Boric Acid /22 2
461 Q
Q Q
Q Q
3 NA RR-6 2
461 4
5 Q
Q Q
3 NA RR-6 Reactor Coolant Charging /21 2
461 4
5 Q
Q Q
3 NA RR-6 Reactor Coolant Charging /22 2
461 4
5 Q
Q 4
3 NA RR-6 Reactor Coolant Charging /23 identified for testing, all pumps are synchronous / induction wound motors a - Other than those Rev. 1 A-11 9/26/88
CALVERT CLITFS NUCIIAR POWF.R PLANT - U IT 2 REQUIRED PUMP TESTS (CONT.)
Inlet Differential Speed" Remarks Pump Name/ Number Class (OM-) Pressure Pressure Flowrate Vibration Lubricant Temperature Ec1t Water /21 3
450 1
Q Q
Q 2
3 NA RR-6
~
Salt Water /22 3
450 1
Q Q
Q 2
3 NA RR-6 Salt Ifater/23 3
450 1
Q Q
Q 2
3 NA KR-6 Service Water /21 3
47 Q
Q Q
Q Q
3 NA RR-6
~
Service Water /22 3
47 Q
Q Q
Q Q
3 NA RR-6 I
Service Water /23 3
47 Q
Q Q
Q Q
3 NA RR-6 Component Cooling /21 3
47 Q
Q Q
Q 2
3 NA RR-6 Component Cooling /22 3
452 Q
Q Q
Q 2
3 NA RR-6 Component Cooling /23 3
451 Q
Q Q
Q 2
3 NA RR-6 Aux. Feedwater/21 2
801 Q
Q 7
Q Q
3 Q
RR-6 Aux. Feedwater/22 2
801 Q
Q 7
Q Q
3 Q
RR-6 Aux. Feedwater/23 2
801 C
Q 7
Q Q
3 NA RR-6 Rev. 1 A-12 9/26/88 I
Unit 2 RELIEF REQUEgT NUMBER 1 Circulating Salt Weter Cooling Aystem:
MID:
OH-450 Salt Water Pumps Nos. 21, 22, and 23 Pumps:
Class:
3
- IWP-3100 requirement to measure inlet Impractical Test Requirement pressure before pump start and during test.
The Salt water pump suction pressure taps do not exist.
Basis for Relief pumps take suction directly from the intake bay through two redundant suction cansla.
Pump suction is situated seven feet below Chesapeake Bay mean Icw water level; therefore, pump suction it a function of bay water level.
(
Chesapeake Bay water level is not considered to change l
during the test.
Bay water level is recorded once during the test and Alternative Testing:
used to compute pump suction pressure.
l l
l l
Rev. 1 A-13 9/26/88
Unit 2 o
RELIEF REQUEST NUMBER 2 Circulating Salt Water Cooling and Component Cooling Water Systee P61D:
OM-450 and OM-452 Salt Water Pumps Noa. 21, 22, and 23 and Component Cooling Water Pumpe Pumps Nos. 21, 22, and 23 Class:
3 IWP-3100 requirement to observe proper Impractical Tost Requirement:
lubricant level or pressure.
The salt water pumps and component cooling pumps have lubricated bearings.
Therefore, observation of Basis for Relief:
grease lubricant level or pressure is not appropriate.
The bearings are greased in accordance with Alternative Testing:
None.
the manuf acturer's instructions on a
regular
)
preventative maintenance actsdule.
4 Rev. 1 A-14 9/26/88
Unit 2 RELIEF REQUEST nut 0lgR 3 Chemical and Volume Control (both Charging and Boric Acid), Low Pressure Safety injection, High Pressure Safety injecti>n, Systems:
Containment Spray, Salt Water Cooling, Component Cooling, Auxili try Feedwater, Service Watnr PiilD's t Various Pur,di t All Safety Related Pumps Class:
2/3 1WP-3100 requirement to measure bearing Impractiral Test Requirement:
temperature.
The refecenced code requires bearing to:perature to be seals for Relief:
recorded annually, it has been demonstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure.
Therefore, the detection of possible by a yearly temperature measurement is bearing failure extremely unlikely.
It requires at least one half hour of pump operation to achieve stable bearing temperatures.
The small probability of detecting bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements.
As an alternative, the pump vibration testing will be expanded f rom one to multiple readings in twn orthogonal directions.
These pumps are part of the Calvert Clifis Vibration Testing Program, and as such, are tested at least on a quarterly basis utilizing a vibration analysis system.
The results of this rigorous analysis provide much more definite information regarding pump mechanical condition than do bearing temperature measurements.
Based upon this, CCNPP does not require annual bearing temperature measurements per the ASME Section XI Code in order to assess pump mechanical condition.
Results of the regular vibration analysis evaluation Alternative Testing:
will be utilized to assess pump mechanical condition at least quarterly, Results of this evaluation will be maintainad as a part of the Prep Rocord.
Rev. 1 A-15 9/26/88
l Unit 2 RELIEF R/. QUEST NUMBER 4 System:
Chemical and Volume Control P&lD:
OM *s61 Reactor Coolant Charging Pumps Nos. 21, 22, an' 23
- Pumps, E
- lass:
2 IWp-3100 requirement to measure pump Impractic.al Test Requirement:
suction pressure The reactor coolant charging pumps n)rmally take their Basis for Relief:
suctinn f rom the outlet of the volume control tank.
The volume control tank is equipped with an automatic make-ep system to prevent low level operation.
If volume control tank level should decrease, a low level alarm is provided action.
to alert the operator to the need for corrective If volume control tank level continues to decrease, a low-low level alarm is actuated and charging pump suction is automatically shifted to the refueling water tank.
Should the charging pumps be starved for flow as the result of a piping rupture or inadvertent valve closure, a
flow rate would be observed and the pump would decreasiPE trip on low suction pressure.
Alternative Testing:
None. The system design discussed above provides adequate indication of and protection from a low suction pressure condition.
Rev. 1 A-16 9/26/88
l Unit 2 RELIEF REQUEST NUMBER 5 Chemical and Volume Control System:
P61D OH-461 Reactor Coolant Charging Pumps Nos. 21, 22 and 23 Pumps:
Class:
2 1WP-3100 requirement to measure pump Impractical Test Requirement:
differential pressure.
Due to pump design, the pump differential pressure is not Basis for Relief:
indicative of pump performance.
Positive displacement a wide spectrum pump differential pressure varies across based on system condition, without a change in flowrate.
Pump flowrate vill to measured and used to assess pump hydraulic condition in lieu of pump differential Alternative Testing:
pressure.
Rev. 1 A-17 9/26/88
Unit 2 RELIEF REQUEST NUMBER 6 System:
As Required Unit 2 P6ID:
Where Applicable Pumps:
As Required Impractical Tant Requirement: Table IWP-4110-1 requires the instrument ar. curacy of the flow instrument used in testing to be i 2% of full sa. ale.
Many of the pumps within the scope of IWP are tested by Basis for Relief:
using ultrasonic or annubar flow meters.
Due to the timef rame of construction for CCNPP, specific test flow monitoring equipment was not part of the original design To install instrumentation meeting the requirement basis.
of Table IWP 4110 1 would require extensive piping In addition, to improve re configuration of most systems.
the accuracy of existing methods would result in extreme for continuous vendor or national labs expense Current re-calibration of instruments between every test.
with the existing instrumentation provides experience confidence that the proposed accuracy will be adequate to determine if e pump is degrading.
All flow measuring instruments will 4eet a loop Alternative Requirement: accuracy of i 4% of full s c a 1.. accuracy.
The repeatability of the instruments will be within thu requirement c' Tabl6 IVP 4110-1.
Rev. 1 A-18 9/26/88 L
Unit 2
(
RELIEF REQUEST MUMBER 7 Auxiliary Feedwater (AW)/High Pressure Safety Injection (HPSI)/ Low Pressure Safety Injection (LPSI)/ Containment Spray (CS).
Syst.ame MIDS:
M-801/462 Pumps:
AW; 21, 22, and 23 HPS!; 21, 22, and 23 LPS1; 21 and 22 Class:
2 and 3 Table lh'P= 3100-2 requires that flow be monitored 1epractical Test Requirement: and maintained within a set allowable range.
These pumps are tested in a mini-recirculation flow loop due to the impracticability of full flow testing during Basis for Relief:
power operation.
The AW, HPSI, LPSI, and CS Pumps, if full flow tested, would result in thermal shock to equipment notales or deluge of equipment in containment with borated water, A recircuicion loop prov! des a relatively fixed resistance flow path.
Tank level does recirculation flow for not have a significant impact on Each of the pumps has a relatively any of these pumps.
flat hydraulic characteristic curve within the Monitoring flow and checking ficw range.
recirculation against an allowable range provides no meaningful input to pump performance.
Quarterly testing will be perforced without evaluating flow.
At each refueling outage a large Alternative Testina flow test will be conducted with flowrate being evaluated along with all other pump vibration and hydraulic performance indicators.
Rev. 1 A-19 9/26/88
[
APPENDIX B EXPLANATION OF CODES AND SYMBOLS USED IN THE CALVERT CLIFFS VALVE INSERVICE TESTING PROGRAM This appendix defires the meaning of all codes and symbols used in the valve test program presented in Appendices C & D.
Rev. 1 B-1 9/26/88
TABLE B-1 i.
SYMBOLS USED TD DESJ_GNA_TE VAINE TYPE VALVE TYPES SYMBOL EANING Check Vali9r C
Butterfly Valve B
Gate Valve G
Clobe Valve GL Pressure Relief Valvs' RV RD Rupture Disk A
Angle Valve Rev. 1 32 9/26/88
TABLE B-2 SYMBOIE USED 'IT) DELGNATE VAT.VE AC'lVATT)R TYPE VAI,VE ACRfATOR TYPES SYMBOL MEANING H
Hotor A
Air Solenoid S
Hand (manual)
H E/H Electro Hydraulic None (self actuating)
Pneumatic Hydraulic P/H i
Hev. 1 B-3 9/26/88
TAB 12 B-3 SYMBOI.S USED 'ID_DESIGNA17. VAIVE POSITION 1
VALVE POSITIONS SYMBOLS MEANING 0
Open G
Shut Calvert Cliffs may revise the identified positions listed in "Normal Position" and "Required Position" based oa changes in valve NOTE:
function.
Rev. 1 B-4 9 26/88 f
TABLZ B-4 SYMBOL 8 USED 111 DESI(Bl&M M8.T!_NG_REQUIREMEKr I.'
si TEST 1
I SYMBOL MEANMG F
Stroke Test per IW-3400 L
Leak Test per 10CFR50, App. J V
Stroke Test of check valves per IW-3520 i
S Set Point Test per IW-3510 I
Isolation Test per IW-3420 (see Section 3.2 of the program)
I RR See Relief Request for testing f
I t
t The symbols shown on Tables B-4 and B-5 will be arranged in the following
(
6
- r. anne r:
A two-letter designation will show Test Method (first letter) and Test Frequency (second letter).
Thus the designation "FQ" relates l
(with timing, as a per IW-3400 A designation of "VC"ppropriate) r to a full-stroke test relates to a check valve j
perfortied quarterly.
exercise test per IW-3520 performed during Cold Shutdowns, j
t i
nese symbols will appear in the "Reg. Test" column as well as the "Alt. Test" l
column, as appropriate.
I i
{
l i
i r
Y f
i I
B-5 Rev. 1 9/26/88 l
l 1
i I
--._.f
. - _ - -, -. - - _ _ _. _ _ _ _.. _ _. _._ _ _ _. ~ _,.. _ _ _,_ _,. _ _- _ _ ______._ _ _ -
p-I TABLE B-5 4 '
t 8YMBOLS USED E DESI(Ri&M M8T FREEIENCY t
f FREQUENCY i
?
SYMBOL MEANING e
Q' Quarterly i
R Refueling t
Per Table IVV-3510-1 T
Cold Shutdown * (Plant in Hodes C
2,3,4,5,6) 7 i
)
Frequency of Cold Shutdown is considered to be whenever the plant achieves l
Specific valves may be tested in Modes 2, 3, 4. or 5
[
a Mode 5 condition.
as appropriate for each valve, (i.e., valves may be tested while achieving I
or recovering from a Moda 5 condition).
i t
6 t
i i
I i
i l
h Rev. 1 i
B6 9/26/88 i
f f
=
s TABLE B-6 r
SYMBOIE USED 10 DE81GNA11 SECTION II VALVE.C&_13 GORY i
i i'
SECTION XI VALVE CATEGORY t
SYNDOL MEAPING t
Valves with specified maximum A
leakaSe rate (pressure system isolation valves (PSIVs) and
-ontainment isolation valves (CIVs)).
Valves with no specific maximum B
t leaksge rate.
Self-actuating (check, relief j
C valves) t Actuated by energy source D
capable of only one operation (rupture
- disks, explosive
),
valves).
j 4
l 2
i I
l t
l f
6 t
i i
l I
r
{
I i
I
(
i Rev. 1 B.7 9/26/88 l
a r
h 5
TABLE B-7 SYMBOI.S USED 11) DESJGNARAprIVE _ AND PASS _I_NG_ VALVES ACTIVE 6 PASSIVE VAL _VES SYMBQL tie _ANING Active - valves which are 1
required to change position to accomplish a specific function.
Passive - valves which are not 2
required to change position to accomplish a specific function.
1 l
1 Rev. 1 B-8 9/26/88
i;,
APPENDIX C 3
CALVERT CLIFFS UNIT 1 I
SECOND TEN YEAR VALVE TESTING PROGRAM i
e P6!D COM-)
EAGE SYSTEM 35 C-1 Main Stena 39 C-2 Condensate and Feedwater C-3
[
46 Service Water t
49 C-5 Salt Water 51 C-7 Component Cooling 53 C-9 Compressed Air 56 C-11 Fire Protection C-12 58 i
Tuol Pool 65 C-13 Ventilation System C-15
.[
66 Post-Accident Sample C-17 68 i
Nitro 8en Blanketing C 18 71 Plant Heating 72 C-19 j
j Reactor Coolant C-20 j
73 CVCS 74 C-24 76 C-30
[
Safety injection Waste Processics C-32 77 RC Vaste Processing C-34 78 i
Wcste Gas 98 C-35 Red. Monitoring C-36 463 i
Gas Analysing 464 C-38 f
8.G. 310wdown C-39 479 Plant Water & Air C-41 i
800 Aux. Feedwater I
k I
(
i l
l i
4 I
2 r
l 1
t l
I i
4 I
1 Rev. 1 j
j 9/26/88 I
r I
ll l
l
~
8 18
/
.6 S
v2 E
e/
R R9 ABM E
1
.T T
TS E
LE A1 E
S LQD MBN 53-MO 4s T
T T
T T
T T
T T
T T
T T
1 T
T C
C 5E S
S S
S S
S S
S S
S S
S S
5 S
S F
F
.T 3T D
45 O
O O
O O
O O
O O
O 0
O O
O 0
0 C
C ON 50 I
EF W5 C
C C
C C
C C
C C
C C
C C
C C
C O
O P
I O0 NF 6
6
)
E c.
I e T (s 1
X X
C S2 O
t F1 H
H c
/
/
P P
e TE he R
AT1 LP V
V V
V V
V V
V V
V V
V V
V V
V L
L dn m
VY R
R R
R R
R R
R R
R R
R R
R R
R G
G a
VE a
T e
n Z m 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 6
6 t
)
3 3
S E
Ii i
S(
a M
TO 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 Y
LG ER E
AE C
C C
C C
C C
C C
C C
C C
C C
C B
B M
VT A
A N
C E
De 6
6 6
5 5
4 4
4 6
6 6
5 5
4 4
4 3
3 M
n I n Y
Ei E
E E
E E
E E
E B
B B
B B
B B
B E
B TS n
S Pr A
2 2
2 2
2 2
2 2
2 2
2 2
2 2
2 2
2 2
s Es WI AC 1
2 3
4 5
6 7
8 9
0 1
2 3
4 5
6 7
3 8
EE 9
9 9
9 9
9 9
9 0
0 0
0 0
0 0
0 4
4 O
VE 9
9 9
9 9
9 9
9 0
0 0
0 0
0 0
0 0
0 N
LS 3
3 3
3 3
3 3
3 4
4 4
4 4
4 4
4 4
4 AI T
VU V
V V
V V
V V
V V
V V
V V
V V
V V
V N
R R
R R
R R
R R
R R
R R
R R
R R
C C
1 1
1
-1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 I
H L
8 I8 f
E
.?
R v2 A
e/
A R9 IWE I
4
.T T
TS LE E
A ENS LQD 9
EEN 3
mE MO
.T QS C
C C
C V
V F
F BM E
ON D
QS C
C C
C 1
EU 5
RF F
E
.S O
O 0
0 W
MO NF
)
E.
Mc 0
0 e
I e 7
7 e
Ts(
ts 2
y S
C X
X 5o r
07n ta w
Tt M
M Er d
r ee T
F d
VE n
LF L
L a
VT C
C G
C 1
ta
)
s E.
n Z m 6
6 6
6 e
I i 1
1 1
1 d
S(
no C
r Er Uu 1
1 1
1 Le E
As C
C B
B M
Vi A
a N
c MI n
T De 7
7 8
8 S
In n
F B
B F
Mn YS s
Es B A 2
2 2
2 1 I AC 1
6 7
1 1
Em 0
3 5
5 VE 3
3 4
4
)K LW 1
1 I
An V
V T
Vu O
O I
n W
W M
M C
1 1
1 1
P&ID NO.
OM-46 SHEET 2
INIT NO.
1 SYSTEM NAME: Servien W t-r Cooling Sy* tem EL.
VALVE ABIE PEID TALTE SIZE VII ACT P05.
TIE NOWt REQ. REQ.
BEQ.
ALT.
MNBER CIA 55 00(EB CA N (im.) TYPE TYPE IM.
(sec.) POS.
POS. TEST M.
TEST BEMEEE O/C O/C VQ 1-SRW-314 3
E-3 C-1 14 C
O/C O/C VQ 1-SRW-315 3
F-3 C-1 14 C
O/C O/C VQ 1-SRW-316 3
C-3 C-1 14 C
O/C O
VQ 1-SRW-317 2
F-6 C-1 8
C O/C O
VQ 1-SRW-318 2
E-10 C-1 8
C i
O/C O
VQ 1-SRW-319 2
H-5 C-1 8
C O/C 0
VQ 1-SRW-320 2
H-8 C-1 8
C C
0 VQ 1-SRW-321 3
F-8 C-1 6
C C
O VQ 1-SRW-322 3
D-8 C-1 6
C O
C VC 1-SRW-323 3
H-2 C-1 18 C
O C
VC 1-SRW-324 3
F-2 C-1 18 C
O C
VC I
1-SRW-325 3
H-2 C-1 18 C
1-CV-1582 2
E-6 B-1 8
B A
X 60 C
O FQ 1-CV-1585 2
E-11 B-1 8
B A
X 60 C
0 FQ 1-CV-1590 2
H-6 B-1 8
B A
X 60 C
O FQ 1-CV-1593 2
F-11 B-1 8
3 A
X 60 C
0 FQ 1-CV-1596 3
B-7 B-1 8
B A
X 15 O
C FQ i
Rev. 1 C-3 9/26/68
UNIT NO.
1 SYS17.M NAME: Servic,t' t r Cooling System P&ID NO.
OM-46 SEET 2
EEL.
VALTE ASIE MID VALUE SIZE VLV ACT P05.
TIfE MMI ESQ. EEQ.
EEQ.
ALT.
PENGER CIASs rnen CATEGIkT (im.) TYPE TTFE IM.
(sec.) P05.
F05. TEST M.
1EST m
1-CV-1597 3
C-8 B-1 8
B A
X IP.
O C
FQ 1-CV-1600 3
B-9 B-1 14 B
A X
30 0
C FC 1-CV-1637 3
B-9 B-1 10 B
A X
30 0
C FC C-4 Rev. 1 9/25/88
l 1
)l
\\Jil l
8 18
/
S
.3 E
v2 R
e/
A R9 N
EE 2
.T T
TS E
LE E
AT HS LQW ME E
64-M O
.T QS C
C Q
Q SE r
F F
F ET ON D
Q5 C
C u
0 E0 I&
RF P
N ES 0
0 0
0 DO MF
)
M c.
0 0
0 0
I e 3
3 2
2 T (s m
5 e
-C t
X X
X X
5M s
0 y
S FI z
TM n
C A
A A
A i
A lo T
oC Vm L
B B
B B
r V
^t T
~-W
)
E c
Z 4
0 6
6 Ii 1
1 iv S(
re S
y Ew Tr 1
1 1
1 Lo E
Au B
B B
B M
Tt A
a N
c ME n
T Da 0
0 8
9 a
1 1
Mm S
F D
Y F
B B
S s
Es I A 3
3 3
3 SI Ac 1
8 9
5 6
Em 3
3 4
4
.O VE 6
6 6
6 N
LE 1
1 1
1 AM T
Vu V
V V
V M
C C
C C
I N
U 1
1 1
1
MID NO.
OM-49 SEET 1
UNIT NO.
1._
SYSTEM NAE: Circ'Irting Salt W ter Cooling System ur VALVE AEK PEID vat 4E SIZE VLY ACT FUS.
TIE MOWI ESQ. REQ.
ESQ.
ALT.
l MENSEE CIASS fYinen CATEGNY (im.) 1TPE TYPE IM.
(sec.) FDS.
F05. TEST ND.
TEST BENARES 1-MOV-5250 3
A-2 B-1 6
B M
X 30 0
C FQ 1-MOV-5251 3
A-3 B-1 6
B M
X 30 0
C FQ a
a Rev. 1 C-6 9/26/88
- - - _ = -.. _.. - _.. -. =. _. - _
l P&lD NO.
OM-47 SHEET 2
UNIT NO.
1 SYSTEM NAME: Circaletinz Salt W ter Coolirm System i
f EEL.
VALVE ASE PEID VALVE SIZE VLV ACT F05.
TIIE lEWI REQ. EEQ.
ESQ.
ALT.
nunusa class coons catsoeur (1.)
TYRE 1TFE Im.
( c.) ras. 70s. 1tsr no.
TusT EnnaEEs O/C O/C VQ 1-SW-103 3
C-11 C-1 30 C
O/C O/C VQ 1-SW-107 3
C-9 C-1 30 C
O/C O/C VQ 1-SW-ill 3
C-6 C~
30 C
i 1-CV-5160 3
E-5 B-1 24 B
A X
15 O/C O/C FQ 5
i 1-CV-5162 3
G-5 B-1 24 B
A X
20 O/C O/C FQ 1-CV-5163 3
H-6 B-?
24 B
A X
24 O/C O/C FQ i
i 1-CV-5170 3
E-3 B-1 8
B A
X 12 O/C 0
FQ 1-CV-5171 3
G-3 B-1 8
B A
X 12 O/C O
FQ 1-CV-5173 3
D-3 B-1 8
B A
X 21 O/C O
FQ
-l 1-CV-5206 3
J-7 B-1 24 b
A X
140 O/C O/C FQ 1-CV-5208 3
H-4 B-1 24 B
A X
148 O/C O/C FQ 1-CV-5210 3
F-10 B-1 30 B
A X
240 O/C O
FQ
~
1-CV-5212 3
H-10 B-1 30 B
A X
254 O/C O
FQ i
l i
Rey. 1 C-7
?/26/88
,------,-,---,,-w-nwy-
---,w
-r---
e
-, - - -. =,
,wi-
--ww--er e
r of.
-wc
--g.+w-
--,,,r-
--w
r=w<1-
UNIT NO.
1 SYSIT*l PULME: Component Coolinz System P&D NO.
OM-51 SHEET 1
EEL.
VALVE ASE FEID VALTE SIZE VLV ALT PUS.
TIM NOME REQ. MQ.
EEQ.
ALT.
NUMBER CIASS CDEMD CATEGENT (im.) 1TFE TYPE IND.
(sec.) 705.
Pos. 1EST ND.
TEST EEMES O/C O/C VQ 1-CC-115 3
E-4 C-1 16 C
i 1-CC-120 3
G-4 C-1 16 C
O/C O/C VQ O/C O/C VQ 1-CC-125 3
J-4 C-1 16 C
2 f
1 i
i I
t i
Rev. I j
C-8 9/26/88
INIT NO.
1_
SYSTEM MAME: Component Cooling System P&ID NO.
OM-51 SMEET 2
EEL.
VALVE ASBE PEIB VALVE SIZE VLV ACT FDs.
TIM NOM MQ. EBQ.
EEQ.
ALT.
Musamt Class coons caincour (im.) Tyre Tvez luo.
(
c.) Pos. Pos. nsT no.
TssT Ennames 1-CV-3824 3
D-6 B-1 16 B
A X
27 O/C O
FQ 1-CV-3826 3
B-6 B-1 16 B
A X
24 O/C O
FQ 1-CV-3828 3
H-9 B-1 16 B
A X
13 C
O FQ
]
1-CV-3830 3
E-9 B-1 16 B
A X
28 C
O FQ
/
1-CV-3832 2
B-1 A-1 10 B
A X
18 O
C FC.IR A-4 CIV j
1-CV-3833 2
J-3 A-1 10 B
A X
18 O
C FC.IR A-4 CIV q
L 1-CV-3840 3
B-7 B-1 10 B
A X
15 O
C FQ 1-CV-3842 3
B-8 B-1 10 3
A X
15 0
C FQ
{
l 7
C-9 Rev. I 9/26/88
---s~
..-.,-,-~-a-
.----,m e-
-~e----,-------
m-
- - -, - - - - - - - - - + - -, - -..,
-w--
M ll 8
1 8 y
/
S
.l 5
6 K
os7 v2 R
V nu1 e/
A I
o-K9 M
C eiA E
vvI R
l e-ar1 E
V p I
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LAE 4
LQO ZEN A
M RR C
.T V.
Q S.
E7 R
R1 L
W QS C
M.
C RS
/
e OO O
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)
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t Mc I e ne Ts(
0 m
1 t
C s
SD n
ON I
AT sy T
S r
VE LP C
i A
VTT de
)
s E
se Z n 2
r_
I i p
S(
mo C
Y ER VO 1
LC AE C
E VT A
A A
N C
M E
D T
DR 0
S I O 1
Y
%O S
I C B
S EE M
ER 7
O VE 3
N LB 3
AM T
VU A
N I
I N
1 L
C-ressed Air System Instrument & Plant MD NO.
_-OM-53 SHEET 3_
LNIT NO.
1_
SYS W. NaME-nsL.
vaunt ansat min vaurs sizz YLv acr ros.
Tim unusi aug. mag.
aug.
ALT.
munnet crass comme catener (i..)
Tyrs Tyrs Inn.
(
c.)
res. res. inst no.
inst seneass l
1-MOV-2080 2
T-1 A-1 2
G M
X 13 0
C IR.FC A-4 CIV l
t l
)
i i
L Rev. I C-11 9/26/88 f
i
LHIT NO, 1
SYSTEM NAfE: Plant Firo Protection System P6D NO.
OM-M _
SMEET 1 EL.
VALVE ASE MIB T&UIE SIZE VIX ACT P05.
TIE SENE EEQ. 50 MQ.
ALT.
NUIRER CIASS CDEMI CATEGERY (im.) TTFE TTFE Ipe.
(sec.) F05.
F05. TEST ND.
1EST MBIAMS C
C IR A-4 CIV 1-FP-141A 2
C-2 AC-2 6
C CIV C
C IR A-4 1-FP-141B 2
C-3 AC-2 6
C CIV C
C IR A-4 1-MOV-6200 3
C-3 A-2 6
G ff X
i Rev. I j
C-12 9/26/88
_ _ _ _ - -. _ _ - ~. _
l i
f' e
8 18
/
s 0
a V
V V
V V
V V
V V
V V
V v2 m
a I
I I
I I
I I
I I
I I
I e/
n C
C C
C C
C C
C C
C C
C R9 nu 2
T. Ts TE Lu AT E
S 4
4 4
4 4
4 4
4 4
4 4
4 L0e 8
z3m A
A A
A A
A A
A A
A A
A 5
aE MO 4s 2
R J
R R
R R
2 2
R R
R
.T L
I I
L I
I I
1 I
L L
t 5u 1
ET ON D
Qs C
C C
C C
C C
C C
C C
C Re l
Er P
ss C
C C
C C
C C
C C
C C
C t
e no uP
)
mc i
s T (.
3 e
1 t
s C
y sm S
o a
rI n
i c
H H
H H
H H
H H
H H
H H
tn l
oo ar C
T l
o LP G
G G
G G
G G
G G
G G
G o
vE P
vYT l
e
)
n 8
8 8
8 2
8 8
8 8
2 8
8 n
F i1 tn s(
ep S
.y ea 2
2 2
2 2
2 2
2 2
2 2
2 tn Ln E
aa A
A A
A A
A A
A A
A A
A M
vT A
a M
C M
T nm 1
1 1
2 2
1 1
0 9
9 9
2 E
e 1
1 1
o B
E C
C C
C C
D D
um S
B B
C YS rc s
3 3
3 3
3 3
3 3
3 3
3 3
ms su 3_
Ac 1
0 1
2 4
6 8
9 0
2 4
6 9
7 7
7 7
7 7
7 8
8 8
8 8
t En v
1 1
1 1
1 1
1 1
3 1
1 1
O a
P P
P P
P P
P P
P P
P P
N Lu T
ve F
F F
F F
F F
F F
F F
F n
5 S
S S
S S
S S
S S
S S
I 0
0 0
0 0
0 0
0 0
0 0
O N
I Il,
!lllt
UNIT NO.
1 SYSTEM NAPE: V.etilation Systems MID NO.
Ort-65 SEET 1__
ML.
VAME ASE MID VMUE SIEE VIX ACT 705.
T~EE IIIME MQ. MQ.
MQ.
ALT.
IEUBEEE CIAss m CSTERIEY (ie.) TTFE TTFE IM.
(sec.) Fes.
FUE. TEST IID.
1EST MIIAMS 1-CV-1410 2
B-11 A-1 48 B
A X
7 C
C IR.FQ VS-1.A-4 RR CIV 1-CV-1411 2
B-11 A-1 48 B
A X
7 C
C IJt.FQ VS-1. A-4 RR CIV 1-CV-1412 2
C-11 A-1 48 B
A X
7 C
C IR,TQ VS-1.A-4 RR CIV RR CIV 1-CV-1413 2
C-11 A-1 48 B
A X
7 C
C IR.FQ VS-1. A-4 v
o Rev. 1 C-14 l
9/26/88 i'------- - -
- C 7y-w y
y
PEID NO.
(M-63 SIEET 2
OIT NO.
1 SYSTEM NA!E: V nttistion System EL.
VALUE ANE 7613 VALWE SIZE VIX ACT F05.
TIE HOME ESQ. MQ.
MQ.
ALT.
IREWER CIASS CDEMI CA190ERY (im.) TTFE TTFE 19 8.
(sec.) FOS.
FUE. TEST NO.
TEST ENEMS C
C IJt A-4 CIV j.HP-104 2
T-4 AC-2 4
C
~
C C
FC,LR A-4 CIV 1-HP-6900 2
G-5 A-1 s
G M
CIV C
C FC,IJt A-4 1-HP-6901 2
G-5 A-1 4
G M
X C
C IJt A-4 CIV 1-HP-6903 2
G-5 A-1 4
G M
X e
1
- )
1 4
1 4'
i 1
Rev. I C-15 9/26/88 W
y--
, +_.-
Reactor Coolant & Water Proces, samp17 P&ID pu.
On-66 _
SEET 1
UNIT NO.
1 _
SYSTDI NA!E:
System Port Accident Samp19 Systee mEL.
vaLys asus pe.no vaunt sizz VLv Act Pos.
Tint most mag. umt.
aug.
ALT.
nungsa Czass coons caTuncer (sm.) Tvrt Tyre Imp. (
c.)
Pos. Pos. inst no.
inst ammauss 1-57-105 1
A-3 B-1 3/4 G
S X
3 C
0 FC A-1 RR 1-SV-106 1
A-3 B-1 3/4 G
S X
3 C
O FC A-1 RR 1-CV-5464 1
C-4 A-1 3/4 G
A X
7 C
C LR.M A-4 CIV l
1-CV-5465 1
3-2 A-1 3/4 G
A X
7 C
C LR,M A-4 CIV CIV 1-CV-5466 1
3-2 A-1 3/4 G
A Z
7 C
C LR.FQ A-4 1-CV-5467 1
C-2 A-1 3/4 G
A X
7 C
C IJt.FQ A-4 CIV 1
Rev. 1 C-16 9/26/88 4
1 a
f' I
8 I8
./
6 v2 V
e/
I R9 C
5 3
.t T
Ts E
Lu E
AT EIS 4
Lep 6
Esu A
6 mu MO
.r gs R
eu L
sT ON qs C
D so aP P
m.s C
u a tsp 1p m
)
a m
ts S
e c
7 t
E.
, s T
s y
(
7 e S 1
co o r l C
X sm P
p o
m r a PI S
t tz e t W n cr S
e av A d i
i t
c n c sE L
iw G
a A v
lo t T
o s C
o
)
P zz ro e I i t
e c t s(
a s e y RS_
r su re 2
uu E
as A
M vT A
a N
c ID m
T n e 1
1 Iw S
s YS rt F
s t s esa 1
sz Ac 1
9 Et 2
ve 5
O Lm 6
N a
T vu V
n S
I N
1 L
P&ID NO.
OM-68__
SEET 1
1] NIT NO.
1&2 SYSTDI NAE: ritromen Generatina. - BI sketing System EEL.
VALVE AEBEE FE Ib MEDE SI2E VLV ACT FUS.
TIME NDEBt ESQ. 550
- E30, ALT.
MUNEFJt CIASS CDDED CETEDDET (in.) TTFE TTFE IND.
(nec.) FUS.
FUS. TEST ND.
1EST BEHAREE5 C
C VQ LR NG-1.A-4 RR CIV O-N -344 2
H-7 AC-1 1
C C
O-N -345 2
H-7 AC-1 1
C C
C VQ,IJt NG-1.?-4 ER CIV y
O-N -346 2
H-7 AC-1 1
C C
O-N -347 2
H-7 AC-1 1
C C
O-N -348 2
H-7 AC-1 1
C C
O-N -349 2
H-7 nC-1 1
C C
O-N -389 2
H-7 AC-1 1
C C
O-N -392 2
H-7 AC-1 1
C C
O-N -395 2
H-7 AC-1 1
C C
O-N -398 2
I'- 7 AC-1 1
C y
Rev. I C-18 9/26/88
P. se0.
OM-71 SIEET 2
LWIT NO.
1 SYSTEM NAPE: Plant Meetinz System I
M1 VALUE ASE FEIB Te&WE SIM VLW ACT pDs.
TIM IEME Eq. MQ.
MQ.
ALT.
museet Csass comum cammaarr (sm.) Tyrs TTrz Im.
(
c.) pas. Pos. nsT suo.
usr amenesus C
C IJE A-4 CIV i
(
0-PH-376 2
A-2 AC-2 3
C 1-MOV-6579 2
B-2 A-2 3
G M
X 13 C
C IJt A-4 CIV 1
l l
i l
l 1
Rev. 1 C-19 9/26/83
)
l l
l
.. _ _ _ -.. _ _ _ _ _ _ _ _ _. _ = -
P&ID NO.
ON-72 _
SIEET 1
INIT NO.
1 SYSTEM MAME: Reactor Coolant Sntes EL.
VALVE AWE 3519 TSENE SIIK TLV ACT FUS.
TIM MM MQ. MQ.
MEl.
ALT.
pagegE CIASS M CENIERY (ie.) TTFE TTFE IM.
(sec.) res.
ME. 1EST 95.
TEST M IIA M E s
- -SV-103 3
J-7 B-1 3/4 G
S X
3 C
O FC A-I 1-SV-104 1
J-6 3-1 3/4 G
S X
3 C
O FC A-1
~
C O
ST T-RV-200 1
B-4 C-1 2 1/2 RV C
O ST 1-RV-201 1
?-8 C-1 2 1/2 RV C
- Electro-1-ERV-402 1
A-5 C-1 2 1/2 RV satic Relief Valve 1-MOV-403 B-5 B-1 4
G M
X 45 O
O M
C 0
- Electro-I-ERV-404 1
A-?
C-1 2 1/2 RV natic Relief Valve 1-MOV-405 1
B-7 B-1 4
G M
X 45 O
O W
7.5 O/C C
FQ.IJt A-4 CIC 1-DW-5460-CV 2
A-11 A-1 2
GL
,A 4
l 1
l Rev. 1 C-20 9/26/88 l
i
y 8
18
/
S 6
E v2 R
e/
A R9 M
ER 1
.F T
TS E
LE E
A1 HS LQD EN ER 3
7 MO QS C
Q Q
C C
C Q
Q Q
Q Q
Q
.T EE V
V V
V V
F F
F F
F F
F RT ON D
QS C
/
/
O O
C O
O C
C C
0 C
C O
O O
HP I&P C
C ES 0
/
/
C C
0 C
C 0
0 C
C M
UO O
O
~
NP
)
0 0
0 0
0 0
0 E c.
3 2
2 3
3 3
2 I e T (s 1
2 X
X X
X X
X X
C SW O
M M
A A
A M
C C
C C
G G
G G
G L
G VE G
VYT 2
2
)
/
/
EZ n 4
3 3
3 3
4 3
3 1
1 3
3 Ii 1
1 S
S(
CVC Y
ER VO 1
(
1 1
1 1
1 1
1 1
1 1
LG E
AE C
C C
C C
B B
B B
B B
B M
VT A
A N
C M
E n
T De 2
8 0
2 6
2 2
8 9
3 4
6 S
In 1
1 1
Y En F
G H
F F
G E
D F
S Pc H
H E
S mA S
2 2
2 2
2 2
2 2
2 2
2 2
sI AC 2
7 2
8 5
1 3
9 4
ER 6
1 2
2 3
0 0
0 0
1 2
1 O
VE 1
2 2
2 2
5 5
5 1
1 1
5 5
5 5
N LW N
C C
C C
C V
V V
V A
T VL V
V V
V V
O O
O V
V V
O I
N C
C C
C C
M M
M C
C C
M W
1 1
1 1
1 1
1 1
1 1
1 1
L l
P&ID NO.
OM-73 SICET 2
UNIT NC.
1 SYSIT.M NAME: CVCS EL.
VALVE ASE PEID VALVE SIZE VLV ACT POS.
TIE NORM REQ. REQ.
BQ.
ALT.
NunmEn CIAss cooRn CAT mneY (in.) TYPE TYPF. IND.
(sec.) POS.
POS. MST NO.
MST Ruants O/C O/C
Q 1-CVC-165 2
E-6 C-1 2
C 1-CVC-171 2
G-6 C-1 2
C O/C O/C VQ O/C O/C VQ 1-CVC-177 2
H-6 C-1 2
C 0
(
1-CVC-184 1
D-5 AC-1 2
C OPEN During Power Oper-ation.-
Tested SHUT During Cold Shutdown.
1-CVC-185 1
C-8 C-1 2
C C
O/C VC 0
O/C VC Tested OPEN 1-CVC-186 1
D-8 C-1 2
C Puring Power Oper-ation.
Tested SHUT During Cold i
Shutoown Tested OPEN 1-CVC-187 1
E-12 C-1 2
C O
O/C VC During Power Oper-ation.
Tested SHUT During Cold Shutdown 1-MOV-269 2
F '.i B-1 2
G H
X 20 C
C FC i
Rev. I C-22 9/26/88
P&ID NO.
OM-73 SHEET 2 _,
LNIT NO.
1 SYSTEM NAME: CVCS REL.
VALVE ASE PEID VALVE SIZE VLV ACT PO3.
TIE NOEM REQ. req.
REQ.
ALT.
Iw!52R r-u" CDORD CATEGORY (in.) TYPE TYPE IW.
(sec.) POS.
POS. "IEST NO.
TEST REMRES C
O ST 1-RV-311 2
G-10 C-1 3/4 RV 1-RV-315 2
E-8 C-1 3/4 RV C
O ST I-RV-318 2
F-8 C-1 3/4 RV C
O ST 1-RV-321 2
H-8 C-1 3/4 RV C
O ST i
1-RV-324 2
H-6 C-1 3/4 RV C
G ST 1
3 j
1-RV-325 2
G-6 C-1 3/4 RV C
O ST C
O ST 0
1-RV-326 2
E-6 C-1 3/4 RV l
1-CVC-435 1
E-12 AC-1 2
C C
1-CV-505 1
B-6 A-1 3/4 GL A
X 7
O C
FC,LR A-4 CIV 1
i l
4 i
Rev. 1 4
C-23 9/26/88
P&ID NO.
OM-73 5HEET 2
UNIT NO.
1 SYSIDI NAME: CVCS REL.
VALVE ASIE PEID VALVE SIZE VLV ACT POS.
TIME NORM REQ. REQ.
REQ.
ALT.
IENBER CIASS COURD CATEGtRY (in.) TYPE TYPE 115).
(sec.) POS.
POS. 1EST NO.
1EST REMARES 1-CV-506 1
B-8 A-1 3/4 GL A
X 7
O C
FC,LR A-4 CIV
+
1-CV-515 1
D-2 A-1 2
GL A
X 13 0
C FC,LR A-4 CIV 1-CV-516 1
D-4 A-1 2
GL A
X 13 O
C FC,LR A-4 CIV 1-CV-517 1
C-10 A-1 2
GL A
X 200 C
O/C FC,LR A-4 CIV j
1-CV-518 1
D-10 A-1 2
GL A
X 53 0
0 FQ,LR A-4 CIV 1-CV-519 1
E-12 A-1 2
GL A
X 38 O
O FQ,LR A-4 CIV v
l 1
i i
i Rev. 1 C-24 9/26/88
l 1
8 1 8
/6 S
v2 ER V
V e/
A I
I R9 M
C C
ER 3
.T T
TS E
LE E
AT HS 4
4 LQC 3
EEN A
A 7
RR MO
.T QS R
R EE L
L R1 ON D
QS EO C
O I&
RP P
t WS OO C
0 NP
)
E c.
fI e as T (s r
5 e
2 v
C SD ec ON i
PI v
G HS VYT s
i
)
5 E
Z n 2
2 0
1 Ii S
S(
C C
V V
C C
Y ER VO 2
2 LG N
E AE A
A E
P M
VT A
A O
N C
s i
M.
D Y
DE 3
3 3
T I0 0
SY E0 B
B 1
PC S
CV S
C ESA 2
2 f
I i
1 l
la 3
5 m
EE 0
0 r
O VI 1
1 o
LB N
N AM C
C T
VU V
V N
C C
I N
1 1
L
UNIT NO.
__ 1 SYSTEM NAME: Safctv InPction & Contninnent Spr'y P&ID NO.
OM-74 SHEET 1-Er?. tea REL.
VALVE ASK 1%ID VALVE SIZE VLV ACT POS.
TIE NORM REQ. EEQ.
REQ.
ALT.
IEllSER CLASS COORD CATECORY (in.) TYPE TYPE ING.
(sec.) POS.
POS. TEST ND.
11ST REN&EES Tested OPEN-C O/C VC 1-SI-113 2
D-2 C-1 2
C During Cold Shutdown.
Tested SHlTT
- )uring Power Operstion.
Tested OPEN 1-SI-123 2
E-2 C-1 2
C C
O/C VC During Cold Shutdown.
Tested SHlTT During Power Operation.
Tested OPEN C
O/C VC 1-SI-133 2
F-2 C-1 2
C During Cold Shutdown.
Tested SHUT During Power Operation.
Tested OPEN 1-S1-143 2
H-2 C-1 2
C C
O/C VC During Cold-Shutdown.
Tested SHUT During Power Operation.
1-SI-401 2
T-9 C-1 6
C C
O VC C
O/C VC 1-51-405 2
F-6 C-1 3
C C
0 ST j
1-RV-409 2
F-4 C-1 3/4 RV Rev. 1 C-26 9/26/68
l.
1li
)
111 8
18
/
S
.0 E
v2 R
e/
A R9 H
EB 1
.T T
TS E
LE E
AT H
S LQO MEN 4
R 7-fPO QS C
C T
Q Q
Q C
C C
Q Q
.T EE V
V S
V V
V V
V V
V V
MT O
C C
C N
C D
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UNIT NO.
1 SYSTEM NAE: Snfc,ty In ketion & Containeest Sprry P&ID NO.
ON-74 SHEET 1
System 1
M.
VALVE ASE PE1O VALVE SIZE VLV ACT POS.
TIE DEMM REQ. REQ.
REQ.
ALT.
IENBER CIAtt CODED CATEGORY (in.) TYPE TYPE 19 5.
(sec.) POS.
POS. TEST 15).
17.ST REMARES 1-MOV-616 2
C-3 B-1 2
GL M
X 20 C
O FQ 1-MOV-617 2
C-3 B-1 2
GL M
X 20 C
O FQ 1-MOV-626 2
D-3 B-1 2
GL M
X 20 C
O FQ 1-MOV-627 2
E-3 B-1 2
GL M
X 20 C
O FQ 1-MOV-636 2
F-3 B-1 2
GL M
X 20 C
0 FQ 1-MOV-637 2
T-3 B-1 2
GL M
X 20 C
0 FQ 1-MOV-646 2
G-3 B-1 2
GL M
X 20 C
O FQ 1-MOV-647 2
H-3 B-1 2
GL M
X 20 C
O FQ 1-MOV-659 2
B-10 B-1 4
G M
X 70 0
O/C FC 1-MOV-660 2
B-10 B-1 4
G M
X 70 0
O/C FC 1-MOV-4142 2
E-10 B-1 18 G
M X
124 0
O/C FQ Tested SHUT Only.
1-MOV-4143 2
F-10 B-1 18 G
M X
128 O
O/C FQ Tested SHUT Only.
C O
VQ SI-6 RR 1-SI-4146 2
E-10 C-1 18 C
C O
VQ SI-6 RR 1-SI-4147 2
F-10 C-1 18 C
C-28 Rev. I 9/26/88
UNIT NO.
1 SYSTEM NAME: Sefaty Inlection & Containment Spray P&ID NO.
OM-74' SHEET 2
System REL.
VALVE ASIE PEID VALVE SIZE VLV ACT POS.
TDE NOEM EEQ. EEQ.
EEQ.
ALT.
IERWEE CLASS N CATEQ(NY (in.) TYPE TYPE Ile.
(sec.) POS. POS. TEST MD.
TEST EENARES 1-SI-114 2
E-3 C-1 6
C C
O/C VC PSIV C
O/C VC,IR 1-SI-118 2
E-4 AC-1 6
C C
O/C VC 1-SI-124 2
J-3 C-1 6
C PSIV 1-SI-128 2
J-4 AC-1 6
C C
O/C VC,IR C
O/C VC 1-51-134 2
E-9 C-1 6
C PSIV 1-SI-138 2
E-8 AC-1 6
C C
O/C VC,IR C
O/C VC 1-SI-144 2
H-9 C-1 6
C PSIV 1-SI-148 2
H-9 AC-1 6
C C
O/C VC,IR 1-RV-211 2
B-2 C-1 1
RV C
O ST 1-SI-215 1
D-2 AC-1 12 C
C O/C VQ,IR SI-3 RR PSIV C
O/C VQ,IR SI-4,5 RR PSIV 1-SI-217 1
D-5 AC-1 12 C
C O
ST 1-RV-221 2
F-1 C-1 1
RV C
O/C VQ,IR SI-3 RR PSIV 1-SI-225 2
E-2 AC-1 12 C
C O/C VQ,IR SI-4.5 RR PSIV 1-SI-227 1
' H-5 AC-1 12 C
X 0
ST 1
1-RV-231 2
B-9 C-1 1
RV C
O/C VQ,IR SI-3 RR PSIV 1-51-235 2
D-9 AC-1 12 C
C O/C VQ,IR SI-4,5 RR PSIV 1-SI-237 1
D-7 AC-1 12 C
1 Rev. 1 C-29 9/26/88 i
~.,. _
8 I8
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1 SYSTEM NAME: Safety In_hetion & Contninnent Spray P&ID NO.
OM-74 SHEET 2
. :- 7 System VALVE ASIE PEID VALE SIZE VLV ACT POS.
TIME N0ftN REQ. REQ.
EEQ.
ALT.
NUMBER CLASS WORD CATunneY (in.) TYPE TYPE IND.
(sec.) POS.
POS. 11ST ND.
1EST RENMIES 1-CV-642 2
F-1 A-1 1
G A
X 6
O/C C
FQ,LR A-4 CIV 1-MOV-645 2
H-10 B-1 6
GL M
X 20 C
0 FQ 1-CV-648 1
G-7 B-1 1
G A
X 30 O/C C
FQ 1-MOV-651 1
J-7 A-1 12 G
M X
108 C
O/C FC,LR A-4 CIV 1-MOV-652 1
J-4 A-1 12 G
M X
102 C
O/C FC,LR A-4 CIV Rev. 1 C-32 9/26/88
LHIT NO.
1 SYSTDI NAME: Safety Inir.cion & Contsinnent Spr y P&ID NO.
OM-74 SHEET 3
a Syetem REL.
VALW ASK FEID VALVE SIZE VLV ACT POS.
TIM NORM REQ. REQ.
REQ.
(sec.) POS.
POS. 17.ST NO.
TESr Remus 1-51-313 2
B-8 C-1 8
C C
O VC SI-7 1-SI-316 2
C-5 AC-1 8
C C
O/C VQ,LR SI-1,A-4 RR CIV 1-SI-323 2
E-8 C-1 8
C C
O VC SI-7 1-SI-326 i
C-4 AC-1 8
C C
O/C VQ,LR SI-1 A-4 RR CIV I-SI-330 2
C-4 AC-1 8
C C
0 VQ 1-SI-334 2
A-9 C-1 2
C 1-SI-340 2
G-4 AC-1 8
C C
O/C VQ,LR SI-1,A-4 RR CIV 1-SI-344 2
E-9 C-1 2
C C
0 VQ 1-CV-657 2
D-4 B-1 12 GL A
X 60/121 C
O/C FQ 1-MOV-658 2
D-7 B-1 12 G
M X
97 C
0 FQ 1-MOV-4144 2
J-5 B-1 24 G
M X
70 C
O/C FQ 1-MOV-4145 2
H-5 B-1 24 G
M X
70 C
O/C FQ 1-SI-4148 2
J-7 C-1 24 C
C O/C VQ SI-2 RR 1-SI-4149 2
H-7 C-1 24 C
C O/C VQ SI-2 RR 1-CV-4150 2
C-3 B-1 8
GL A
X 60 C
0 FQ 1-CV-4151 2
G-3 B-1 8
GL A
X 60 C
O FQ Rev. I C-33 9/26/88
1
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4 LWIT NO.
1 SYS1TM NAME: Reacter Ceolant Vastm Proc w inz System P&ID NO.
Orf-77 SHEET 3
EEL.
VALVE AspE MID VALVE SIZE VLV ACT POS.
TIM NUESI REQ. EEQ.
EEQ.
ALT.
I BERGER CIA 55 CODED CATEGORY (ia.) TYPE TYPE IIE).
(sec.) POS.
POS. 1TST NO.
1EST EENARICE 1-ES-142 3
E-9 A-2 1
GL H
C C
LR A-4 CIV C
C LR A-4 CIV 1-ES-144 3
E-9 A-2 1
GL H
i l
J
}
i i
Rev. I t
C-37 9/26/88 l
j
^
SNIT NO.
1 SYSTEM NAME: Wasta Gas & Mire. Vmtra Procnming P&ID NO.
OM-78 SEET 1
Systems
-il a
REL.
VALW.
A5BE PEID VA'.TE SIZE VLV ACT POS.
T17E NDEM REQ. LEQ Taq.
ALT.
i 3ENBER CIASE fvman CA1100EY (ir..) TYPE TYPE 19 9.
(sec.) POS.
POS. TSST IE).
1EST REMARES 1-CV-2180 2
C-2 A-1 2
GL A
X 7
O/C C
LR.FQ A-4 CIV I-CV-2131 2
C-2 A-1 2
GL A
X 7
O/C C
LR,FQ A-4 CIV t
O l
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l
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1 1
C-38 j
9/26/88 1
l
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A 9
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1 1
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m P&ID NO.
OM-463 SHEET 1
LHIT NO.
1 SYSTEM NAME: Ca3 Annlyzing System 3,
~
REL.
valve Asut psID VALM SIZE VLV ACT POS.
TIfEE NORN REQ. req.
REQ.
ALT.
Museum Crass ennen CATEGOstY (im.) TYPE TYPE Ipe.
(sec.) POS.
POS. HST ND.
TEST RDeamKK 1-SV-6507A 3
B-9 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 1-SV-6507B 3
B-2 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 1-SV-6507C 3
B-2 A-2 1/4 GL S
X 3
C C
LR A-1 A-4 RR CIV 1-SV-6507D 3
B-3 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 1-SV-6507E 3
3-10 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 1-SV-6507F 3
B-10 A-2 1/4 GL S
X 3
C C
1-SV-6531 2
E-5 A-2 1/4 GL S
X 7
C C
1-SV-6540A 3
B-9 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 1-SV-6540B 3
B-2 A-2 1/4 GL S
X 3
C C
j I
1-SV-6540C 3
B-2 A-2 1/4 GL S
X 3
C C
.f 1-SV-6540D 3
B-3 A-2 1/4 GL S
X 3
C C
1-SV-6540E 3
B-10 A-2 1/4 GL S
X 3
C C
1-SV-6540F 3
B-10 A-2 1/4 GL S
X 3
C C
f 1
Rev. I l
C-40 9/26/88 f
P&ID NO.
Ort-463 SHEET 2
UNIT NO.
1 SYSTD1 NAME: Gas Analyzinz System mEL.
VALVE ASIE FEID VALVE SIZE VLV ACT POS.
TIIE IWEN REQ. ESQ.
EEQ.
ALT.
NuecEn Class ennen CATEcour (im.) TrPE TYPE IND.
(sec.) FOS.
POS. 1HST NO.
TEST EEMBES 1-SV-6507G 3
H-6 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 1-SV-6540G 3
G-6 A-2 1/4 GL S
X 3
C C
8 e
f
^!
Rev. 1 l
C-41 9/26/88 i
1
LWIT NO.
1 SYSTIM NAME: Stram Generrtrr Blowdown Recovery P&ID NO.
OM-464L SHEET 1
EEL.
VALVE ASK PEID VALVE SIZE VLV ACT POS.
TIM IEEN REQ. EEQ.
EEQ.
ALT.
3RNMER CIASS - CATsonmY (im.) Tf7E TYPE DS.
(sec.) 705.
P05. TEST ND.
1EST REMBES 1-CV-4010 2
D-2 B-1 2
G A
X 30 O/C C
FQ 1-CV-4011 2
E-2 B-1 2
G A
X 30 O/C C
FQ I-CV-4012 2
B-2 B-1 2
G A
X 30 O/C C
FQ 1-CV-4013 2
C-2 B-1 2
G A
X 30 O/C C
FQ Rev. I C-42 9/26/88 y--
_=
LHIT NO.
1 SYSTDI NA*.fE:
Plant t!cter & Air Servica System P&ID NO.
OH-479 SEEET 1
- Strtion, M.
VALVE ASIE PEIB VALVE SIZE VLV ACT FOS.
TIIE MOME BEQ. EEQ.
EEQ.
ALT.
MuMEEE Class rman CAlmanaf (im.) TYPE TYPE IND.
(sec.) FOS.
F05. TEST ND.
TEST REMBES 1-PSV-1008 2
J-3 A-2 3
GL H
C C
IR A-4 CIV 4
l C-43 Rev. 1 9/26/88
OM-479 SHEET 2 __
g.
LNIT NO.
1 SYS m NAME: Plant W-tar & Air Servica Synters P&ID NO.
Strtions EEL.
TALTE ASE MID YALVE SIZE VLV ACT POS.
TITE m EEQ. ESQ.
EE4 ALT.
PasWER CMSS rnnen CATEGERY (la.) TYPE *1YPE 1953.
(sec.) FOS.
POS. TEST Is.
TEST BEntBES 0-PSV-1019 2
D-6 A-2 3
G H
C C
LR A-4 CIV l
1-PA-1040 2
D-2 A-2 2
G H
C C
LR A-4 CIV:
CIV C
C LR A-4 1-PA-1044 2
F-8 A-2 2
G H
L-Rev.;1 C-44 9/26/88
s J,
lil llljiJ r
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C C
C C
Q C
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C C
C C
C C
C Q
EE V
V V
V V
V V
V V
V V
V V
V V
V V
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C C
C C
D QS
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0
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WL
Unit 1 RELIEF REQUEST NUMBER A-1 System:
Various PM D:
Various Valves:
Various valves which have actual stroke times of 2 seconds or less Category: A and B Active Class:
Various IWP-3413 to measure valve stroke time to Impractical Test Requirement:
the nearest second, and associated trending requirements of IWV-3417.
Basis for Relief Valves with extremely short steoke, times (less than 2 seconds) have stroke times of such short duration that comparison of measurements with previous data for specified percentage increases is not indicative of degrading valve performance.
With measurement of stroke times to the nearest second per IWV-3'+13(b), a very small increase in stroke time will result in an extremely largs percentage change, which could reault in an unnecessary increase in test frequency and challenges to valves.
Verificiation that valves meet a specified maximum stroke time of short duration provides adequato assurance of operability.
Alternative Testing:
Only the maximum stroke time will be verified for those valves with nominal stroke times less than 2 seconds.
The trending requirements of IWV-3417(a) will, therefore, not apply.
I i
t i
t r
b Rev. 1 l
C-48 9/26/88 l
l l
t g
i Unit l' RELIKF REQUEST NUMBER A-2 System:
Various P61D:
Various Valves:
Various soinnoid actuated valves Category: A and B Active CIass Various IW-3300 requirement to locally versi; Impractical Test Requirement:
remote position indicatien at least on e t
every 2 years.
l t
Basis for Relief:
Relief req'sest withdrawn i
Alternative Testing:
I
?
l i
i i
I r
C-49 9/26/88 6
Unit 1 I
RELIEF REQUEST NUMBER A-3 System:
As Required, Unit 1 P61D:
Where Applicable Valves:
As Required Category: C Cleast As Required Functient Relief Protection on Various Systems l
IW-3512 requires compliance to ASME PTC Impractical Test Requirement:
25.3-1976.
Paragraph 3.02 of PTC 25.3, 1977 Addendum,
- requires, "A
person who supervises the test shall have a formal education in thermodynonics and fluid mechanics.
In addition, he shall have at least two years practics1 experience in fluid flow measurement and have had experience in test supervision."
l Basis For Relief:
The requirement of ASME PTC 25.3-1976 for thc qualifications of a relief valve test supervisor are burdensome to a utility.
It would result in addtional staff requirements that are not warranted in light of the alternate means of meeting the intent of this paragraph.
The Plant Operating Safety Review Committee Alternative Requirements:
reviews all test procodures and any unacceptable results of relief valve testing.
There are typically several members of this committee that meet the educational and experience level requirements of the Code.
All test results are reviewed by the System Engineer responsible for the components i.. the system the relief valve protects.
The personnet who conduct the tests meet specific qualification requirecients in 1978.
All accordance with ANSI /ASME N45.2.6 instruments used for testing are calibrated within the scope of the site Quality Assurance requirements.
Rev. 1 C-50 9/26/48
Unit 1 RELIEF REQUEST NUMBER A-4 System:
Various P61D:
Various Velves:
All those idnntified with."CIV" in the Remarks column of the associated Valv6 Test Program.
Class t Various Impractical Test Requirements:
a.
IWV-3421 through 3425 regarding leak rate test methodology.
b.
IWV-3427(b) regarding leak rate trending requirements.
In keeping with NRC Staff position, all CIV testing Basis For Relief:
- a..
shall be performed under 10CFR$0 Appendix J in additional to IWV-3426 and IWV-3427(a).
Testing per 10CFR50 Appendix J meets the intent of leak rate testing per Section XI, but will be controlled via the Local Leak Rate Testing Program.
b.
The attached data shows that the variability of leak 4
rates for valves 6 inches and larger is excessive.
CCNPP feels that this excessive variability shows the relative independence of one leak rate test to l
another.
The tendency towards random feak rate data would cause unnecessary testing per IWV-3427(b), with no identifiable increase in benefit to public health and safety.
The worth of performing this additional trending is also called into question by the recent ASME approval of OM-10
("Inservice Testing of L
kalves"), which is the planned replacement to Section XI testing rules. OM-10 does not require trending of valve leak rates.
CCNPP shall test all CIVs under the requirements Alternative Testina:
a.
of 10CTR50 Apprendix J, in addition to IWV-3426 and IWV-3427(a).
b.
CCNPP shall perform no alternative testing Asi keeping with OM-10 guidance.
Rev. 1 C-51 9/26/88
Unit 1 RELidF REQUEST NUMBER V8-1 1
System:
Ventilation System 1%ID:
OM 65, Sh.1 1-CV-1410, 1-CV-1411, 1-CV-1412, 1-CV-1413 Valves:
Category: A-1 Class:
2 Function: Containment Isolation IW-3400 requirement to stroke test ti.e Impractical Test Requirement:
valves quarterly.
nese valve are normally locked shut with powc. removed.
Basis for Relief:
only required to stroke in Mode 6.
It is not desirable to stroke test these valves during each cold They are shutdown since unnecessary stroking could damage the sealing surfaces of these valves, causing degradation of leak-tight capabilitj.
This would result in the valve's an unnecessary increase in testing and valve maintenance.
n e valves will be full stroke tested on a refueling Alternative Testina:
frequency.
t l
L k
Rev. 1 C-52 9/26/88
-,,n-
Unit 1 gi RELIEF REQUEST NUMBER NG-1 i
System:
Nitrogen Generating and Blanketing System P61D:
OH-68 0 N2-344, 0-N2-345, 0-N2-346, 0-N2-347, 0 N2-348, 0-N2-349, Valves:
O N2-389, 0 N2-392, 0 N2-395, 0-N2-398 l
l Category: AC-2 Class:
2 IWV-3520 requirement to full-stroke Impractical Test Requirement:
exercise the valves quarterly.
Basis for Relief:
These containment isolation valves are normally shut, passive valves.
A quarterly test to ensure the valves are closed is not possible without using LLRT-type equipment, and making an entry into containment.
These valves will be leak tested on a refueling Alternative Testina:
schedule in accordance with the Calvert Cliffs Appendix J Program.
i f
1 1
1 1
Rev. 1 C-53 9/26/88
Unit 1 l
Rst.Isr RzqUEST NUMBER RC-1 System:
Reactor Coolant MID:
OH-72 Valves:
1-ERV-402, 404 Category: C-1 Class:
1 Function: Relieve reactor coolant pressure.
Impractical Test Requirement:
Setpoint test per IWV 3510.
These valves are categorized per Calvert Cliffs Technical Basis for Relieft Specifications as ASME Section XI Category C-Active (relief valve).
However, due to the unique valve design, these valves cannot be tested per IW-3510, since the valves are actuated as the result of an electrical signal from a pressure measurement device opening these valves Alternative Testing:
Valves are tested per Technical Specificati.cs at refueling intervals.
The test includes a channel calibration of the actuation channel.
A channel functional
- test, excluding valve operation, is perforwed within 31 days prior to entering a condition when this valve is required to serve as an MPT relief, and every 31 days thereafter when the valves are required to be operable.
In addition, these valves will be functionally tested each cold shutdown prior to placing them in service for lov Temperature Overpressurization Protection.
I i
i Rev. 1 C-54 9/26/88 1
i t
Unit 1 RELIEF REQUEST NUMBER SI-1 System:
Safety Injection and Containment Spray P61D:
OM-74, Sh. 3 Valves:
SI-316, SI-326, SI-330, SI-340 Category: AC-1 Class:
2 Function: Containment Spray Header inlet checks, inside and outside containment isolation valves.
Impractical Test Requirement: IWV-3520 requirement to exercise the valves once every 3 months.
Check valves SI-316, SI-326, SI-330, and SI-340 cannot be Basis for Relief stroked during operation without spraying large quantities of centaminated water into the containment.
This contaminated refueling pool water is also borated to Spraying the containment would approximately 2300 ppm.
result in a radiometive contamination cleanup problem and seriously damage components such as lagging, reactor coolant pumps, and control rod element assembly coils.
One vr.1ve will be disasse241cd at each refueling Alternative Testing:
If outage to inspect the valve internal components.
degradation is found that would result in the valve being unable to pass full design flow, then all I
valves will be inspected in the same refueling outage.
3 Rev. I C-55 9/26/88
Unit 1 RELIEF REQUEST NUMBak SI-2 System:
Safety injection and Containrent Spray F6tD:
OM-74, Sh. 3 Valves:
SI-4148, SI-4149 Category: C-1 Class:
2 Function: Containment Sump Outlet Check Valves lepractical Test Requirement: 1W-3520 requirement to exercise valves once every 3 months.
These check valves cannot be full-stroke exercised without Basis for Relief:
flooding the containment floor with contaminated refueling pool water that is borated to approximately 2300 ppm.
This would result in serious damage to lagging and electrical systems control components in addition to the radioactive contamination cleanup problem of the containment sump and associated equipment.
One valve will be disassembled at each refueling Alternative Testing:
outage to inspect the valve internal components.
If 4
degradation is found that would result in the valve i
being unable to pass full design flow, then all valves will be inspected in the same refueling l
outage.
i 4
Rev. 1 C 56 9/26/88 1
_ _, ~ ~ _. _ _ _,, _ _ _ _ _ _,. _ _ _.. _ _ - _ _ _ _ _
r U"It I t
RET.IEF REQUES't NUNDER SI-3 System:
Safety Injection MID:
OH-74, Sh. 2 Valves:
1-SI-215, 1 SI-225, 1-51-235, 1 S1-245 Category: AC-1 Class:
1 Functica: Safety Injection Tank discharge ch6ek valves, pressure system isolation valves Impractical Test Requirement: IW-3520 requirement to full-stroke exercise valves.
3 asis for Relief:
It is not possible to measure the flowrate through these valves nor to simulate rapid depressurization of the RCS.
Additionally, achieving the design flowrate through these valves would require removal of the reactor vessel head and the flowrate required could cause damage to the core internals.
Alternative Testing:
One valve will be disassembled at each refueling outage to inspect the valve's internal coa'ponent s.
If degradation is found that would result in the valve being unable to pass full design flow, then all valves will be inspected in the same refueling outage.
Rev. 1 C-57 9/26/88
- - _ - _ = -.. - - _
- c Unit 1 REIIEF REQUEST PLUMBER SI-4 System:
Safety Injection MID:
OM-74, Sh. 2 Valves:
1-SI-217, 1-SI-227, 1 SI 237, 1-SI-2!7 Category: AC-1 Class:
1 Safety Injection to RCS loop check valves, pressure inolttion valves Function:
IW-3400 requiresent to test the valves' Impractical Test Requirement: pressure isolation fonction.
Basis for Reliet:
The pressure upstream of these valves is continuously monitored, and an increase teruits in an alarm in the control room, which requires operator action in accordance with the Calvert Clif fs alarm manual, nis manual would require the operator to determine the leakage rate through these valves.
Alternative Testing:
Pressure upstream of these valves is continuously monitored and an increase will be alarmed in the control room.
This continuo 1s monitoring provides assurance that these valves are mea 61ng their pressure isolation safety function.
C-58 Rev. 1 9/26/88
Unit 1 t
RELIEF REQ 0EST NUMBER SI-5 whL t
Systems Safoty Injection P61D:
OH-74, Sh. 2 Valves:
1-51-217, 1-51-227, 1-SI 237, 1-SI-247 Category: AC 1 Class:
1 t
Safety injection to RCS loop check valves, pressure isolation valves i
f Function:
IVV-35 0 requirement to full-stroke exercise the Impractical Test Requirement: valves.
l is not possible to measure the flowrate through these It f
Basis for R(lief:
valves nor to simulate rapid depressurization of the RCS, Additionally, achieving the design flowrate through these valves would require a reaoval of the reactor vessel head and the flowrate required could cause damage to the core internals.
The valves are part stroked whenever shutdown cooling Alternative Testing:
One valve will be disassembled at is in operation.
l each refueling outage to inspect the valve's internal If degradation is found that would 2
components.
in the valve being unable to pass full design result flow, then all valves will be inspected in the same refueling outage.
l t
t l
Rev. 1 C-59 9/26/88
RELIEF REQUEST NUMBER SI-6 h
System:
Safety Injection PEID:
OM-74 Velves:
1-S1-4146, 1-SI-4147 Category: C t
Class:
2 Funct).on: Refuel _ng Water Tank Outlet Check Valves Impractical Test Requirement: IWV-3520 requires a check valve to be tested to its design flow position once a quarter.
It is not possible to provide full design flow through Basis for Relief:
these check valves during any period of plant operation.
The full design flow would require the simultaneous operation of 1 LPSI pump, 1 CS pump, and 1 HPSI pump for each valve with the combined discharge path that duplicates the design basis LOCA.
It is not possible to provide simultaneous full design flow from all three pumps due to core damage from excessive teactor vessel flow and deluging of containment interior components from the spray header.
These valves vill be part-stroke tasted once a Alternative Testina:
quarter.
One valve will be disassembled at each refueling outage to inspect the valvo's internal If degradation is found that would i
components.
result in the valve being unable to pass full design flow, then all valves will be inspected in the same refueling outage.
1 r
i t
Rev. 1 C-60 i
9/26/88
Unit 1 t
RELIEF REQUEST NUMBER SI-7 System:
Containment Spray P61D:
OM-74 Valves:
1 51-313, 1-SI-323 Category: C Class:
2 Function: Containment Spray Pump Discharge Check Valve IW-3520 requires a check valve to be tested to Impractical Test Requirement: its design flow position once a quarter.
These valves cannot be full-flow stroke tested due to Basis for Relief:
limitations on the bypass discharge flow patht.
The valves can be full flow tested only during refueling outages where plant conditions can be established to allow the use of both Containment Stray pumps as alternate LPSI to provide Shutdown Cooling flow.
The core decay pumps heat load is minimal and the need for a boration flow path dependent only on one charging pump occurs during refueling outages only.
On a COLD SHUrDOWN basis, the valves will be Alternative Requirements:
part-stroke tested. The valves will be rull Stroked each refueling outage during the Large Flow testing of the respective Containment Spray pumps.
Rev. 1 C-61 9/26/88
APPENDIX D CALVERT CLITFS UNIT 2 SECOND TEN YEAR VALVE TESTING PROGRAM P&ID (OM-)
EAGE SYSTEM 36 D-1 Main Steam D-2 40 Condensate and Feedwater 46 D-3 Service Water D-4 47 Service Water
$6 D-5 Fire Pretection D-6 65 Ventilation tystem D-8 66 Post-Accident Sample D-10 71 Plant Heating D-11 76 Waste ProcessJng D-13 77 R.C. Vasto Processing D-15 78 Waste Gas D-16 9e Rad. Monitoring D-17 450 Salt Water Cooling D-19 452 Component Cooling D-21 454 Compressed Air D-22 460 Reactor Coolant D-23 461 CVCS D-27 462 Safety Injection D-33 463 Gas Analyzing D-35 465 S.G. Blowdown D-36 479 Plant Water & Air D-38 801 Aux. Feedwater Rev. 1 9/26/88
il l
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2
UNIT NO.
2 SYSTEM NAME: Cordenset, and Feedwat r Systee P&ID NO.
OM-40 SHEET 6
asL.
vm amat vs.In valve sizz TLv Acr ros.
TIME nten mag. amQ.
mEQ.
ALT.
nunusa crass mnen caTmoor.! (im.) 1Trz Tmt Im.
(
c.)
Pos.
res. Tust m.
TusT muunnes 0
C VC 2-W-130 2
F-7 C-1 16 C
0 C
VC 2-W-133 2
B-7 C-1 16 C
2-MOV-4516 2
B-8 B-1 16 G
M X
70 0
C FC 2-MOV-4517 2
F-8 B-1 16 G
M X
70 0
C FC Rev. 1 D-2 9/26/88 i
l INIT NO.
2 SYSTEM MAME: Servic, f'ater Coolina System P&lD NO.
OM-47 SMEET 2
1
=
EEL.
VALVE AspE MID VAIJpE SIZE VLV ACT POS.
TIME MOIBE REQ. Eng.
EgQ.
ALT.
MNSEE CIAgg nman CATBIEMY (Is.) TYPE TYPE IW, (sec.) FOS.
FUS. TEST W.
TEST EIM M S 2-CV-1645 3
F-8 B-1 6
B A
X 20 C
0 FQ 2-CV-1646 3
D-9 B-1 6
B A
X 20 C
O FQ Rev. I E-3 9/26/88 1
,i
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2
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- j 8
I8
./
s 3
m v2 a
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a R9 n
um 2
.T T
Ts E
Ls A1 E
S LQo 7
EEn 4
ER MO
.T Qs Q
C C
C C
St F
F F
F F
EE O
N D
Qs C
C C
C C
I S0 E7 P
I W s.
0 0
0 0
0 Do NP
)
2.
5 0
0 0
0 Ec I e 0
3 3
3 3
Ts 1
(
5 m
e D
t Sc X
X X
X X
sy On S
FI g
TE n
CF A
A A
A A
i AT lo T
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Lr Vr B
B B
8 B
-t T
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)
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8 4
4 4
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1 1
1 1
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B B
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1 1
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A B
A B
s E s Ea 3
3 3
3 3
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7 0
7 8
9 9
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3 3
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5 6
6 6
6 O
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1 1
1 N
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Vu V
V V
V V
n C
C C
C C
I NU 2
2 2
2 2
=.
. i i
- i 1
8 I8 S
/
E 3
R V
V V
v2 A
I I
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N C
C C
R9 EE 1
.T T
TS I
LE AT W
S 4
4 4
LQD MESN A
A A
65-M O
.T R
R t
QS J
E I
L L
MT ON D
Q5 C
C C
I E0 EF P
M5 C
C C
D0 NF
)
M c.
I e T (s m
6 e
t X
D 5M s
0 y
S FI no TE i
CF M
t AT c
T e
to VE r
LF C
C G
P VTT er
)
iF E
Z m 6
6 6
t I i n
S(
a l
P Y
EE ND 2
2 2
I e E
A3 C
C A
T1 A
A
!A A
N C
M E
a T
Bm 8
9 8
Em I
S C
C C
Y S
Pc 5
E5A 2
2 3
BI AC 2
0 A
B 0
ER 5
5 2
O VE 4
4 6
N LB 1
1 AM V
T VU P
P O
I N
F I
M N
U 2
2 2
ICIY NO.
_2_
SYSTDt NAE: Ventilation System P&ID NO.
OM-65 SMIT 1
EL.
VALVE ABE PEIB TALUE SIEE VLF ACT F05.
TIM NUME 113Q. BQ.
MQ.
ALT.
MERGER CIASS nmnen CATEGIEY (Ja.) TTFE TYPE IIG.
(sec.) 705.
F3R. TEST ND.
TEST EBRAME 2-CV-1410 2
B-11 A-1 48 B
A X
7 C
2-CV-1411 2
B-11 A-1 48 B
A X
7 C
}
2-CV-1412 2
C-11 A-1 48 B
A X
7 C
)
2-CV-1413 2
C-11 A-1 48 B
A X
7 C
'i 1
0 l
l I
i D-7 Rev. I 9/26/88
LHIT NO.
2 SYSTEM NAPE: Ventilation Systee P613 NO.
OM-65 53EET 2
s.
VALVE ASE WEID VALWE SIZE VLW ACT 705.
TIfE DEmel BEQ. MQ.
MQ.
ALT.
umumt Cuss couan cassunuY (s.) TYPE TYPE Ise. ( c.) Pos. Pos. Tust m.
m~r immamms C
C IJt A-4 CIV 2-HP-104 2
T-4 AC-2 4
C t,
C II.IR A-4 CIV 2-H?-6900 2
G-5 A-1 4
G M
X r
C C
FC,IJt A-4 CIV 2-HP-6901 2
G-5 A-1 4
G M
X C
C IJt A-4 CIV 4
I l
2-HP-6903 2
G-5 A-2 4
G H
X i
r a
i l
\\
1 i
I 1
i i
1 a
I I*V-1 p.g l
9/26/88 1
CIT NO.
2 SYSTEM MafE: Beacter Coolant & f~at r Process Samp17 PEID NO.
_ Off-66 _
SHEET 1
System Post Accident Samp17 Systee asL.
vaus asus vsta vaut sizz vu er ros.
T1am muses usa. nog.
seg.
ALT.
museum c ass cosmo casuonar (1..) TYPE Tyre lem.
(sec.) Pos.
Pos. TEST ND.
1EsT EENANss ESV-105 1
A-10 B-1 3/4 G
S X
3 C
0 FC A-1 RR ESV-106 1
A-11 B-1 3/4 G
S X
3 C
tr FC A-1 RR 2-CV-5464 1
C-10 A-1 3/4 G
A X
7 C
C IR,IT}
A-4 CIV 2-CV-5465 1
B-11 A-1 3/4 G
A X
7 C
C IR,FQ A-4 CIV 2-CV-5466 1
B-11 A-1 3/4 G
A X
7 C
C IR.FQ A-4 CIV
~
2-CV-5467 1
3-11 A-1 3/4 G
A X
7 C
C IR,TQ A-4 CIV I
i l
+
Rev. 1 i
i D-9 9/26/88
~ -. -.
LWIT NO, 2
SYSTDI M4fE: Reactor Coolant & Water Process Samp!_,
P&ID NO.
OPf-46 SEEZT 3
System Post Acc.ident Samp1, System mEL.
VALK ASE MIS VALUE SIZE VLV ACT res.
TIM MBE BAQ. MQ.
MQ.
ALT.
numet class ennen ca m murr (im.) Tyre Tyre Ise.
(sec.) Pos. Pos. TusT m.
1ssT wannet 2-SV-6529 1
E-11 A-2 GL 5
X 7
C C
IJt A-4 CIV
^
N
~
Rev. 1 D-10 9/26/88
LHIT NO.
2 SYSTEM MAME: Plant h ating System MID NO.
OM-71 SEET 2
EL.
TALVE AM MID VALK SIZE TLV ACT F05.
TIM MDM REQ. MQ.
REQ.
ALT.
9ENGER CIAss CD M CATEDDET (im.) TYFE TYPE 1853 (sec.) FOS.
POS. N 2.
TEST N
C C
LR A-4 CIV 0-PH-387 2
C-12 AC-2 3
C H
2-MOV-6579 2
E-11 A-2 3
G M
X 13 C
C LR A-4 CIV I,
l 1
l l
l i
s Rev. I D-11 9/26/88 i
UNIT NO.
2 SYSTEM NUE: West Process Equipment _& Area Dr ins P&D NO.
OM-7 3 _
SMET 2
M L.
VALTE ASNE MIB V8MNt SIEE VLV ACT FUS.
TIM NDIBE EEQ. 330 EBQ.
ALT.
nunaut cIAss coons catammer (im.) TTFE TYPE 11er.
(sec.) Pos. res. 1sst no.
last ansaamas 2-MOV-5463 2
J-6 A-1 4
G M
X 1*
O/C C
IR.FQ A-4 CIV J
i l
1 i
i 1
Rev. 1
{
D-12 9/26/88 2
LHIT NO.
2 SYSTIM MA!E: Westo Proces, Equipment & Area Dr-ins P&ID NO.
OM-76 SHEET 4
ML.
VALUE ASE 7613 VAIAE SIEE TEX ACT F05.
TIM IsmE MQ. MQ.
MQ.
ALT.
letsamt CIASE ccEER CaculmY ($m.) TYPE TTFE 13 8. (sec.) 705.
F05. TEST ND.
TEST REEAME 2-790V-5462 2
C-6 A-1 4
G t
I 13 O/C C
IR.FQ A-4 CIV Rev. I D-13 9/26/88
WIT NO.
2_
SYSTEK MME: Reactor Coolset Westo Prrxessinz Systee P&ID No.
art-77 smET I
asL.
VALUE ACBE I%IB VapE SIEE VEX ACT 19s.
TIfE NDEN MQ, MQ.
MQ.
ALT.
Nunusa cuss conus emanney (1.)
TYPE Tyrs Inn.
( c.) ms. Pos. inst m.
TusT usumans 3-CV-4260 2
D-7 A-I CL A
X 7
O/C C
p.34 9/26/88
UNIT NO.
2 __
SYSTEM NAME: Reacter Coolant Wirta Proces,ing System P&ID NO.
OM-77 SHEET 3
REL.
VALVE AM PEID VALVE SIZE VLV ACT POS.
TIPE N[EN REQ. EEQ.
BBQ.
ALT.
BENWER CritK CODED CATynnNY (in.) TYPE TYPE IN3.
(sec.) POS.
POS. TEST
.DE).
1EST REMMES 2-ES-142 3
E-9
. A-2 1
GL H
C C
LR A-4 CIV 2-ES-144 3
E-9 A-2 1
GL H
C C'
LR A-4 CIV Rev. I D-15 9/26/88
UNIT NO.
2 SYSIT.M NAME: Wastn Gas & Mirc. Vasta Procesr:inx P&ID NO.
_ OM-78
. SHEET 1
Systems EEL.
VALVE ASIE PEID VALVE SIZE VLV ACT POS.
TDE NORM REQ. EEQ.
EEQ.
ALT.
MUIRER CIASS rnnen CATmurY (in.) TYPE TYPE IND.
(sec.) POS.
POS. TEST ND.
17.ST REN&EKS 2-CV-2180 2
D-2 A-1 2
GL A
X 7
O/C C
LR,FQ A-4 CIV 2-CV-2181 2
D-2 A-1 2
GL A
X 7
O/C C
LR,FQ A-4 CIV l
Rev. 1 D-16 9/26/88
LHIT NO.
2 SYSIT.M NAME: Arm & Proc ^ta Radiction Monitrring P&ID NO.
OM-98 SEET System REL.
VALVE ASIE PEID VALVE SIZE VLV ACT POS.
TIfE NEEN REQ. REQ.
REQ.
ALT.
NUMBER CMSS CODED CATEGOItY (im.) TYPE TYPE IND.
(sec.) POS.
POS. TEST 10 0.
TEST EDeaMER 2-CV-5291 2
C-9 A-1 1
GL A
X 7
0 C
FQ,LR A-4 CIV l
2-CV-5292 2
C-10 A-1 1
GL A
X 7
O C
FQ,LR A-4 CIV 3
i Rev. 1 D-17 9/26/88
i a
8 I 8
/
S
. 0 K
v2 R
e/
A R9 M
ER 1
.T T
TS E
LE E
AT HS 0
LQD 5
EEN 4
RR MO
.T QS Q
Q EE F
F R1 ON D
QS C
C I
M ES O
0 DO m
NP e
ts
)
E c.
y 2
0 S
I e 2
3 g
Ts(
n 8
i 1
l o
o SW X
X D
O C
M V
AYT t
la VE S
LP B
B VY g
T n
i t
)
E l
Z n 6
6 u
I I c
S(
r i
C Y
ER VO 1
1 LG
- E AE B
B M
YT A
A N
C ME D
T DE 3
2 S
ID Y
EO A
A S
PC KM 3
3 SAL 2
0 1
5 5
ER 2
2 O
VE 5
5 N
LB A N V
V T
V E O
O I
I M
M N
U 2
2 1
UNIT NO.
2 SYSTEM NAME: Circulcting Salt Wr.tcr Cooling System P&ID NO.
OM-450 SHEET 2 _.
,+
REL.
VALVE ASE MID VALVE SIZE VLV ACT POS.
TIE NORM REQ. REQ.
EEQ.
ALT.
MUMBER CIASS C00ED CATEGORY (in.) TYPE TYPE 12.
(sec.) POS.
POS. TEST ND.
TEST REMEES 2-SV-103 3
C-6 C-1 30 C
O/C O/C VQ 2-sw-107 3
C-9 C-1 30 C
O/C O/C VQ O/C O/C VQ 2-sw-lil 3
C-12 C-1 30 C
2-CV-5160 3
E-4 B-1 24 B
A X
24 O/C O/C FQ 2-CV-5162 3
G-4 B-1 24 B
A X
27 O/C O/C FQ r
2-CV-5163 3
J-4 B-1 24
.B A
X 26 O/C O/C FQ 2-CV-5170 3
F-3 B-1 8
B A
X 15 O/C O
FQ 2-CV-5171 3
G-3 B-1 8
B A
X 15 O/C O
FQ 2-CV-5173 3
E-3 B-1 8
B A
X 22 O/C 0
FQ 2-CV-5206 3
J-7 B-1 24 B
A X
124 O/C O
FQ 2-CV-5208 3
J-6 3-1 24 B
A X
106 O/C O/C FQ 2-CV-5210 3
D-10 B-1 30 B
A x
140 O/C 0
FQ 2-CV-5212 3
H-10 B-1 30 B
A X
278 O/C O
FQ
'I Rev. 1 D-19 9/26/88
121IT NO.
2 SYSTEM NAME: Component Coolinst Systes P&ID NO.
OM-452 SHEET 1
'W REL.
VALVE ASE PEID VALVE SIZE VLV ACT POS.
TIE NORM REQ. REQ.
REQ.
ALT.
NUISER CIASS COURD CATEGORY (in.) "ITPE TYPE IE.
(sec.) POS.
POS. TRST W.
TEST RENAMM 2-CC-115 3
J-4 C-1 16 C
O/C O/C VQ 2-CC-120 3
C-4 C-1 16 C
0/C O/C VQ 2-CC-125 3
E-4 C-1 16 C
O/C O/C VQ Rev. 1 D-20 9/26/88
8 18
/
S
.6 E
V V
v2 R
I e/
C C
R9 AM ER 2
T TS i
L.
L1 t
A*1 r.
S 4
4 2
QD 5
EN A
A 4
R
-M O
R R
.T L,
L, Q
Q QS Q
Q Q
Q EE F
F F
F C
C F
F F
F RT ON D
QS 0
O O
O C
C C
C I
C C
/
/
C C
O 0
0 0
OO O
0 NP
)
E c.
f 5
9 5
6 8
8 5
0 I e 2
2 4
3 1
1 1
2 T (s 1
2 S)
X X
X X
X X
X X
D m
OM e
PI tsy Ts S
C A
A A
A A
A A
A m
A g
n i
l VE o
LP B
B B
B B
B B
B o
VY C
T tn
)
E n
Zn 6
6 6
6 0
0 0
0 Ii 1
1 1
1 1
1 1
1 m
S(
c Y
ER VO 1
1 1
1 1
1 1
1 LG E
AE B
B B
B A
A B
B M
VT A
A N
C M
D DR 6
6 9
9 2
4 8
9 S
I0 Y
E0 B
C G
E A
H A
A S
PC S
NA S
3 3
3 3
2 2
3 3
4 6
8 0
2 3
0 2
ER 2
2 2
3 3
3 4
4 O
VE 8
8 8
8 8
8 8
8 N
LW 3
3 3
3 3
3 3
3 A R T
V R V
V V
V V
V V
V I
I C
C C
C C
C C
C N
U 2
2 2
2 2
2 2
2 n
~
UNIT NO.
2 SYSTDI NAME: Comprcmed Air Syotes: Plant &
P&ID NO.
OM-454 SEET 3
Instrument Air EEL.
VALVE ASK PEID VALVE SIZE VLV ACT POS.
TIE NOWt BEQ. REQ.
REQ.
ALT.
IENBER CIASS Cnnen C&TunnNY (in.) TYPE TYPE 12.
(sec.) POS.
POS. 11ST NO.
W.ST BENARES O/C C
C-7 AC-1 2
C 2-MOV-2080 2
C-7 A-1 2
G M
X 13 O
C LR,FC A-4 CIV l'
j l
i l
i Rev. 1 D-22 9/26/88
UNIT NO.
2 SYSTEM NAME:
R, actor Coolant System P&ID NO.
OM-460 SHEET 1
EEL.
VALWS ASK PMD
~ VALVE SIZE VLV ACT POS.
TIE MEN REQ. EEQ.
EEQ.
ALT.
NUrre2 CLASS cnnen CATunnmY (im.) TYPE TYPE Ile.
(sec.) POS.
POS. TEST ND.
1EST RENARES 2-SV-103 1
J-6 B-1 3/4 G
S X
3 C
O FC A-1 2-SV-104 1
J-5 B-1 3/4 G
S X
3 C
O FC A-1 1
C O
S~
2-RV-200 1
B-4 C-1 2 1/2 RV 2-RV-201 1
B-7 C-1 2 1/2 RV C
0 ST C
- Electro-
{
2-ERV-402 1
A-4 BC-1 2 1/2 RV matic re-1 ief valve l
1 2-MOV-403 1
B-4 B-1 4
G M
X 45 0
0 FQ 2-ERV-404 1
A-7 BC-1 2 1/2 RV C
- Electro- -
matic re--
lief valve 1
l 2-MOV-405 1
P-6 B-1 4
G M
X 0
0 FQ 2-DW-5460-CV 1
A-10 A-1 2
GI A
X 7..
0/C C
FQ,LR A-4 CIV l
l l
1 i
l Rev. 1 D-23 f
9/26/88
)
li1 83 S
/G H
2
/
M 9
E R
1
.T T
TS LAE EEH S
1 LQD EN mR 64-HO
.T QS C
Q Q
C C
C Q
Q Q
Q Q
Q EE V
V V
V V
F F
F F
F F
F RT ON C
C D
QS C
/
/
O 0
C 0
0 C
C C
0 EU O
O I&
RP P
C C
C ES O
/
/
C C
0 C
C 0
0
/
C N
0 DO 0
O NP
)
E c.
0 0
0 0
0 0
0 3
2 2
3 3
3 2
I e Ts(
42 SD X
X X
X X
X X
M M
A A
A M
AT1 VE LP C
C C
C C
G G
G L
L G
G G
G VIT 2
2
)
/
/
E.
Zn 4
3 3
3 3
4 3
3 1
1 3
3 I I 1
1 S
S(
CVC Y
Ee Vn 1
1 1
1 1
1 1
1 1
1 1
1 L
Am C
C C
C C
B B
B B
B B
A N
C M
D T
Dm 2
6 9
2 4
2 0
6 7
0 3
5 S
I 0 1
1 I
G H
F F
F E
C F
Y Eo F
t i
G E
S Pc
~
s MsA 2
2 2
2 2
2 2
2 2
2 2
2 7
2 8
5 1
8 9
4 Et 6
1 2
2 3
0 0
0 0
1 2
1
?
2 2
2 2
5 5
5 1
1 1
5 O
Ve N
Ls 5
5 5
An C
C C
C C
V V
V V
T Vu V
V V
V V
O O
O V
V V
O I
N C
C C
C C
M M
M C
C C
M N
U 2
2 2
2 2
2 2
2 2
2 2
2
P&ID NO.
OM-461 SHEET 2
UNIT NO.
2 SYSTEM NAME: CVCS REL.
VALVE ASIE PEID VALVE SIZE VLV ACT POS.
TIfE NDEM REQ. REQ.
REQ.
ALT.
NLNBER CIASS CODED CATEGORY (in.) ITPE TYPE IND.
(sec.) POS.
POS. TEST ND.
TEST REMARES 2-CVC-165 2
F-6 C-1 2
C O/C O/C VQ 2-CVC-171 2
G-6 C-1 2
C O/C O/C VQ 2-CVC-177 2
J-6 C-1 2
C O/C O/C VQ 2-CVC-184 1
E-5 AC-1 2
C 0
O/C VC, LR A-4 CIV, Tested OPEN During Power Oper-ation.
Tested SHUT During Cold Shutdown 2-CVC-185 1
C-8 C-1 2
C C
O/C VC Tested OPEN h-CVC-186 1
E-8 C-1 2
C 0
O/C VC During Pow-Operation.
Tested SHUT During Cold Shutdown Tested OPEN 2-CVC-187 1
E-11 C-1 2
C 0
O/C VC During Pow-Operation.
Tested SHUT During Cold Shutdown 2-MOV-269 2
G-4 B-1 2
G M
X 20 C
C FQ 2-RV-311 2
G-9 C-1 3/4 RV C
O ST 2-RV-315 2
F-8 C-1 3/4 RV C
0 ST Rev. 1 D-25 9/26/88
- 1 l
8 I8
/
N 6
ER V
V V
v2 I
I I
e/
AE C
C C
R9 IER 2
. T T
TS E
LE E
A1 HS 4
4 4
1 LQD A
A A
6 EEN 4
RR M
O C
C C
.T V,
F, F,
QS T
T T
T T
EE S
S S
S S
R R
R L
L L
RT ON C
D QS O
0 0
O O
/
C C
O I
M RS C
C C
C C
C O
O OO NP
)
E.
E c 7
7 II e Ts(
62 SD X
X D
A AYT VE LP V
V V
V V
C L
L VY R
R R
R R
G G
T
)
E.
4 4
4 4
4 4
4 Zn
/
/
/
/
/
2
/
/
Ii 3
3 3
3 3
3 3
S S(
CVC Y
Ee Vn 1
1 1
1 1
1 1
1 Ln E
Ar C
C C
C C
C A
A A
M VT A
A N
C M
E D
T DR 8
8 6
6 6
0 8
6 S
IU 1
Y EO G
H H
G F
B B
F S
PC S
L S A
2 2
2 2
2 1
2 2
5 ER 8
1 4
5 6
3 5
6 O
VE 1
2 2
2 2
4 0
0 N
LB 3
3 3
3 3
5 5
AM C
T VU V
V V
V V
V V
V N
R R
R R
R C
C C
I N
U 2
2 2
2 2
2 2
2
P&ID NO.
OM-461 SHEET 2
LHIT NO.
2 SYSIDi NAME: CVCS REL.
VALVE ASIE 1%ID VALVE SIZE VLV ACT POS.
TILE NORM REQ. REQ.
REQ.
ALT.
MIISER CIASS CDORD CATEGOilY (in.) TYPE TYPE IE.
(sec.) FOS.
POS. TEST ND.
TEST RENAME 2-CV-515 1
D-3 A-1 2
GL A
X 13 0
C LR,FC A-4 CIV 2-CV-516 1
D-4 A-1 2
GL A
X 13 0
C LR,FC A-4 CIV 2-CV-517 1
C-9 A-1 2
GL A
X 200 C
O/C FC,LR A-4 CIV 2-CV-518 1
E-9 A-1 2
GL A
X 24 0
0 LR,FQ A-4 CIV 2-CV-519 1
E-10 A-1 2
GL A
X 18 O
O LR,FQ A-4 CIV Rev. 1 D-27 9/26/88
P&ID NO.
OM-461 SEET 3 _
UNIT NO.
._ 2 SYSTEM NAME: CVCS REL.
VALVE ASK FEID VALVE SIE VIX ACT POS.
TIM NOIEN REQ. REQ.
REQ.
ALT.
NWWER CIASS nnnen CA1EGORY (in.) TYPE TYPE Ile.
(sec.) POS.
P05. U.ST ND.
1EST RENAME C*
C*
IR A-4 CIV 2-CVC-103 2
B-3 A-2 2
G H
2-CVC-105 2
B-3 A-2 2
G H
0*
O*
IR A-4 CIV Normally if CVC-103 is OPEN, CVC-105 is SHITT, and vice versa.
O Rev. 1 D-28 9/26/88
INIT NO.
2 SYSTIM NAME: Safrty Ialection & Contninment Spray P&ID NO.
Orf-462 _
SHEET 1
Systes REL.
VALVE ASIE PEID VALVE SIZE VLV ACT POS.
TIPE NDEN REQ. REQ.
REQ.
ALT.
NLMWEE CIASS rnnen CATur:nsrY (in.) TYPE TYPE Ilm.
(sec.) POS.
PDS. "IEST 10.
11ST BEMMIS Tested OPEN C
O/C VC 2-SI-113 2
D-2 C-1 2
C During Cold Shutdown.
Tested SHlTT During Pow-er Oper-ation.
Tested OPEN 2-SI-123 2
E-2 C-1 2
C C
O/C VC During Cold
. Shutdown.
Tested SHUT During Pow-er Oper-ation.
Tested OPEN 2-SI-133 2
F-2 C-1 2
C C
O/C VC During Cold Shutdown.
Tested SHUT During Pow-er Oper-ation.
Tested OPEN C
O/C VC 2-51-143 2
G-2 C-1 2
C During Cold Shutdown.
Tested SHUT During Pow-er Oper-ation.
Rev. I D-29 9/26/88
~
~
8 18
/
SE 6
R v2 A
e/
N R9 ER T
.r T
Ts E
LE E
A1 HS 2
QO EN 6
M 4
M O
.T QS C
C T
C C
T Q
Q Q
C C
C Q
EE V
V S
V V
S V
V V
V V
V V
ET 3N C
C C
C C
D QS 0
/
O O
/
O O
0 O
/
/
/
O I
EO O
O O
O O
RP P
N C
C C
C C
C C
C C
C C
C C
MSO P
I y
rr
)
M c.
p S
I e t
Ts n
(
0 e
3 m
n D
i 9 S2 a
O t
P1 no C
VE t
LP C
C V
C C
V C
C C
C C
C C
c VY R
R b
T m
I
)
4 E
v m Z n 6
3
/
8 3
1 2
2 2
6 0
0 2
1 1
t e
Ii 3
t S(
-:f s
a y
S S
Y EN Vn 1
1 1
1 1
1 1
1 1
1 1
1 1
Ln E
4r C
C C
C C
C C
C C
C C
C C
M VE AN C
M 7
n 7
De 9
5 4
9 5
4 8
8 8
5 4
5 8
S In Y
En G
G F
E E
D E
C F
D H
C B
S Pr S
KA S
2 2
2 2
2 2
2 2
2 2
2 2
ER 1
5 9
0 4
7 2
4 6
7 4
6 8
O VE 0
0 0
1 1
1 2
2 2
2 3
4 4
N LS 4
4 4
4 4
4 4
4 4
4 4
4 4
AI T
VU I
I V
1 1
V I
1 I
I I
I 1
I N
S S
R 5
5 R
S S
S S
S S
5 N
U 2
2 2
2 2
2 2
2 2
2 2
2 2
... = -
UNIT NO.
2 SYSTEM NAME: Safety Inisction & Contcinzent Spray _
P&ID NO.
OM-462__
SHEET 1
Sy ten REL.
VALVE ASIE PEID YALVE SIZE VLV ACT POS.
TIIE NDEN REQ. REQ.
REQ.
ALT.
DetBGER CLASS COEMD CATEGEMY (im.) TYPE TYPE Ile.
(sec.) POS.
POS. TEST ND.
TEST REN4RES C
O VQ 2-SI-451 2
G-8 C-1 2
C 2-MOV-616 2
D-3 B-1 2
GL M
X 20 C
0 FQ 2-MOV-617 2
C-3 B-1 2
GL M
X 20 C
0 FQ 2-MOV-626 2
E-3 B-1 2
GL M
X 20 C
0 FQ 2-MOV-627 2
E-3 B-1 2
GL M
X 20 C
O FQ y
2-MOV-636 2
F-3 B-1 2
GL M
X 20 C
0 FQ 2-MOV-637 2
F-3 B-1 2
GL M
X 20 C
O FQ 2-MOV-646 2
H-3 B-1 2
GL M
X 20 C
O FQ 2-MOV-647 2
G-3 B-1 2
GL M
X 20 C
O FQ 1
2-MOV-659 2
A-10 B-1 4
G M
X 70 0
O/C FC 2-MOV-660 2
B-10 B-1 4
G M
X 70 0
O/C FC Tested SHUT 2-MOV-4142 2
E-10 B-1 18 G
M X
106 0
O/C FQ Only.
Tested SHUT 2-MOV-4143 2
D-10 B-1 18 G
M X
108 0
O/C FQ Only.
C 0
VQ SI-6 RR 2-SI-4146 2
E-10 C-1 18 C
C 0
VQ SI-6 RR i
2-SI-4147 2
E-10 C-1 18 C
I Rev. 1 D-31 9/26/88
i ill 8
I8
/
N V
V V
V V
V V
V 6
v2 I
I I
I I
I I
I S
S S
S S
S S
S e/
P P
P P
P P
P P
R9 2
.T T
TS E
LE AT E
R R
R R
S R
R R
R 5,
5, 3
3 4
4 LQO I
I 2
S I
S I
MEN 6
E S
S 4
-MO C
C C
C R
Q Q
Q I,
V, V,
V,
.T V,
V, V,
V, T
T T
C C
C EE V
R V
R V
R V
R S
Q R
S R
R S
QS C
V I
I I
ET I
I I
I O
C C
C C
C C
C C
C C
C C
N D
QS
/
/
/
/
/
/
/
/
O
/
/
O
/
/
O EO O
O O
O O
O O
O O
O O
O I&
EP P
MS C
C C
C C
C C
C C
C C
C C
C C
M.
O MP ar
)
E c.
p S
I e T (s tn 2
e 3
n i
SD n
D n
ON t
AYT no r
LP C
C C
C C
C C
C V
C C
V C
C V
i VE R
R R
c VY T
i a
)
I y m Z n 6
6 6
6 6
6 6
6 1
2 2
1 2
2 1
E 1
1 1
1 t e Ii e
t S(
f s a y S S Y
Vn 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
Ea Lo E
As C
C C
C C
C C
C C
C C
C C
C C
M VT A
A A
A A
A A
A A
A K
C M.
n T
De 3
4 3
4 9
9 9
9 3
3 6
3 3
S 9
T S
In Y
En D
D H
H D
D M
H B
C D
F G
H B
S Pe s
a 2
1 2
1 2
1 2
1 2
1 1
2 1
1 2
ms sz AC 2
Ea 4
8 4
8 4
8 4
8 1
5 7
1 5
7 1
O Ft 1
1 2
2 3
3 4
4 1
1 1
2 2
2 3
1 1
1 1
1 1
1 1
2 2
2 2
2 2
2 N
Da A
I I
I I
I I
I 1
V I
I V
1 I
V T
Vmu S
S S
S S
S S
5 R
S S
R 5
S R
I 2
2 2
2 2
2 2
2 2
2 2
2 2
2 2
W llllll 1l11ft l
ll llllllll'
UNIT NO.
2 SYS17.M NAME: S-fnty In_lection & Conainment Spray P&ID NO.
OPf-462 SEET 2
System REL.
VALu Ases min VALu sIzz VLv Act POS.
THE NUEff REQ. REQ.
REQ.
ALT.
nunEnt c Ass ennen canoosnr (im.) TYPE TYPE IM.
(sec.) POS.
POS. MST ND.
TEST REM &RES C
O/C IR,VQ SI-3 RR PSIV 2-SI-235 1
C-9 AC-1 12 C
2-SI-237 1
D-7 AC-1 12 C
C O/C IR,VQ SI-4,5 RR PSIV C
O ST 2-RV-241 2
F-9 C-1 1
RV C
O/C IR,VQ SI-3 RR PSIV 2-SI-245 1
G-9 AC-1 12 C
C O/C IR,VQ SI-4,5 RR PSIV 2-SI-247 1
G-7 AC-1 12 C
4 i
Rev. 1 i
D-33 9/26/88 4
h f
8 18
/
s u
V V
V V
V V
6 r
I I
v2 p
C C
C C
C C
e/
I I
a I
I R9 ER 2
.T T
TS E
LE E
AT HS 4
4 4
4 4
4 6
EEN A
A A
A A
A LQO 2
4 EE O
R R
R R
M
.T L,
L, L,
L, Q
Q Q
Q Q
Q 5E F
L L
S S
Q F
F Q
F F
Q F
F Q
9S Q
R R
T T
F F
F F
ET O
D Q5 C
C C
0 O
C 0
C C
O C
C O
C C
N E0 I
RP C
C C
C C
C C
P MS C
C C
C C
/
C
/
/
C
/
/
C
/
/
H O
O O
O O
O O
O E P I
y r
)
0 6
0 0
6 0
0 6
0 0
6 rp E c.
l 2
3 2
3 2
3 S
I e 2
T (s 4
tr 3
e S)
X X
X X
X X
X X
X X
X e
D n
E i
OI a
H H
A M
A A
M A
A M
A A
o TE C
AT1 n
LP G
G G
V V
L L
L L
L L
L I
L L
o VE c
VY R
R G
G G
C G
G G
G G
G i
t e
T f
n 2
)
y m
Z n 2
2 2
1
/
1 6
1 1
6 1
1 6
1 1
/
4 I
E 3
I i t
e 1
t S(
f 7
a r.
S S Y
VO 1
2 2
1 1
1 1
1 1
1 1
1 1
1 1
ER LG E
AE B
A A
C C
A B
B A
E E
A B
B A
M VT A
A N
C T
Du 6
8 8
8 5
5 3
5 5
3 5
1 0
7 7
M n
1 1
E r
Y Er H
B B
J J
B D
C F
H G
C F
S Iw B
D S
Pr S
A 2
2 2
2 2
2 2
1 2
2 1
2 2
1 2
5 5
5 ER 9
5 3
8 9
2 1
8 2
2 8
2 3
8 2
9 O
VE 3
5 6
6 6
1 6
1 2
6 2
3 6
3 4
4 4
4 4
6 6
6 6
6 6
6 A B V
V V
V N
LS T
V E O
1 I
V V
V O
V V
O V
V O
V V
I I
M 5
S R
R C
M C
C M
C C
M C
C N
2 2
2 2
2 2
2 2
2 2
2 2
2 2
2 I
INIT NO.
2 SYSTEM NAE: Safety Injection & Contninnent Spray.
P&ID NO.
Ort-462 SHEET 2
Syntes EEL.
VALTE ASK PEID 3ALTE SIZE VI.V ACT POC.
TIE SE M I EEQ. EEQ.
EEQ.
ALT.
NIEEER CIASS CODED CATannmY (is.) "1TPE TYPE Ile.
(sec.) 708.
POS. TLTT IW.
TEST EIMMIS 2-MOV-645 2
H-10 B-1 6
GL M
X 20 C
O FQ 2-CV-648 I
G-7 B-1 1
GL A
X 30 O/C C
FQ I
Rev.'1 D-35
(
9/26/88
8 18 S
./
E 6
R V
V v2 A
I I
e/
M C
C R9 ER 2
T. TS TE LE A1 E
S 4
4 2_
LQG 6
EE3 A
A 4
ER MO R
R
.T L,
L, QS EE C
C E1 F
F ON C
C D
QS
/
/
I EO O
O RP P
N ES C
C E O B P yar
)
E n.
9 8
p 0
0 S
II e 1
1 t
Ts n
(
e 6
n 3-n 55 X
X D
i r
09 t
M AYT no i
VE t
LP G
G c
VY e
T f
n I
)
E y
m Z n 2
2 t
e I i 1
1 t
S(
f s
a y
SS f
Esr Vn 1
1 Ln E
Ay A
A M
VT A
A N
C ME n
T Da 7
5 S
I n Y
Ln J
J i
S Pr S
ESA 1
1 BtI AC 2
1 2
ER 5
5 O
VE 6
6 N
LB A
V V
N T
V E O
O I
I M
M N
U 2
2 4
iI i!
~
UNIT NO.
j.t_
SYSIT.M NAME: Scfety Injection & Contcinment Spray _
P&ID NO.
OH-462__
SEET 3
System EL.
VALVE ASIE FEID VALE SIZE VLV ACT F05.
TIE NORM REQ. EEQ.
EEQ.
ALT.
M3mER CIASS mnen CATEG0Kf (im.) TYPE TYPE 19 5.
(sec.) POG.
F05. TEST ND.
TEST BEHARES C
B-8 C-1 8
C
~-
C O/C LR,VQ SI-1,A-4 RR CIV 2-SI-316 2
D-4 AC-1 8
C C
2-SI-323 2
F-8 C-1 8
C 2-51-326 2
G-4 AC-1 8
C C
O/C LM.VQ SI-1, A-4 RR CIV 2-51-330 2
D-3 AC-1 8
C 2-SI-334 2
A-9 C-1 2
C C
O/C VQ 2-SI-340 2
G-3 AC-1 8
C C
O/C VQ 2-51-344 2
E-9 C-1 2
C 2-CV-657 2
E-4 B-1 12 CL A
X 79/86 C
O/C FQ 2-MOV-658 2
E-7 B-1 12 G
M X
92 C
O FQ 2-MOV-4144 2
J-S B-1 24 G
M X
70 C
O/C FQ 2-MOV-4145 2
H-S B-1 24 G
M X
70 C
O/C FQ 2-SI-4148 2
J-7 C-1 24 C
C O/C VQ SI-2 RR C
O/C VQ SI-2 RR 2-SI-4149 2
H-7 C-1 24 C
2-CV-4150 2
C-3 B-1 8
GL A
X 60 C
0 FQ 2-CV-4151 2
F-3 B-1 8
GL A
X 60 C
O FQ Rev. 1 D-37 9/26/88
1 P&ID NO.
OM-463_
SHEET, _
LNIT NO.
2 SYSTEM NAME: Gas Anmlyzing System REL.
-n.
TALVE ASIE FEID VALVE SIZE VLV ACI POS.
TIE NtEN REQ. REQ.
REQ.
ALT.
pasmE2 r rat. s enran CATEGtRY (im.) TYPE TYPE 12.
(sec.) POS.
POS. TEST MD.
TEST REMRES 2-SV-657A 3
B-3 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 2-SV-6507B 3
B-11 A-2 1/4 CL S
X 3
C C
LR A-1,A-4 RR CIV 2-SV-6507C B-11 A-2 1/4 GL S
X 3
C C
B-12 A-2 1/4 GL S
X 3
C C
LR A-lea '+
B-4 A-2 1/4 GL S
X 3
C C
2-SV-6507F 3
B-4 A-2 1/4 GL S
X 3
C C
2-SV-6531 2
E-5 A-2 1/4 GL S
X 7
C C
LR A-1.A-4 RR CIV 2-SV-6540A 3
B-9 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 2-SV-6540B 3
B-11 A-2 1/4 GL S
X 3
C C
LR A-1 A-4 RR CIV 2-SV-6540C 3
B-11 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 2-SV-6540D 3
B-12 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 2-SV-6540E 3
B-4 A-2 1/4 GL S
X 3
C C
2-SV-6540F 3
B-4 A-2 1/4 GL S
X 3
C C
i i
Rev. 1 D-38 9/26/88 w-.,
-w r
-wwm--ip-y w a gn=
--w-,
w n
y g
wvv~
n--
w
+*
,wr
-m-
- i- - - -
P&ID NO.
_ OM-463 SHEET 2
LNIf NO.
2 SYSTEM NAME: Gas Analyzing System EL.
VALVE ASIE FEIB YALTE SIZE VLV ACT POS.
TIM NDEN REQ. EEQ.
EEQ.
ALT.
NUISEE CIASS rnnen CATunnmY (in.) TYPE TYPE 19 5.
(sec.) F05. F05. 115T ND.
'IEST REMARES 2-SV-6507G 3
J-9 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV 2-SV-6540G 3
H-9 A-2 1/4 GL S
X 3
C C
LR A-1,A-4 RR CIV Rev. 1 D-39 9/26/88
8 18 5
./
6 E
v2 E
e/
4 R9 N
ER 1
.T T
TS E
LE AT E
S 5
LQD 6
EEN 4
EE M
O
.T QS Q
Q Q
Q EE F
F F
F ET ON D
QE C
C C
C EO I&
RP P
N.
C C
C C
/
/
/
/
ES E O G
O O
O B P
)
E c.
y 0
0 0
0 re I e 5
3 3
3 v
Ts o
(
0, c
1 D
R SD X
Z X
X n
ON w
PI o
dw TE o
CP A
A A
A AY l
B T
re VE t
LP L
L L
L r
VY G
C G
G r
T en
)
eG EZ 2
2 2
2 Ii m
a S(
e t
S r
Eu To 1
1 1
1 Lc E
Au B
B B
B
~
M TT A
A N
C M
E n
T Be 2
2 2
2 S
ln Y
En D
E B
C i
S Pr 5
Ma s
2 2
2 2
z AC 2
0 1
2 3
Ea 1
1 1
1 O
Us 0
0 0
0 N
Ls 4
4 4
4 Aa T
V V
V V
T M
C C
C C
I N
2 2
2 2
I
LHIT NO.
2 SYSTEM NAME: Plaut W t-r & Air Servic, System P&ID NO.
OM-479 SHEET 1-Strtions EEL.
VALVE ASIE FEID VALVE SIZE VLV ACT POS.
TIIE NDME EEQ. EEQ.
EEQ.
ALT.
DRESEE CIASS rnnen CATunnmT (im.) TYPE TYPE IM.
(sec.) FOS.
POS. 115T IE).
TEST EnthEE5
~
C C
LR A-4 CIV 2-PSW-1009 2
J-9 A-2 3
GL H
l Rev. 1 D-41 9/26/88
~.. _ _.
CNIT NO.
2 SYSTEM MAME: Plant f* t r &_ Air Servic, System P& D NO.
OH-479 SHEET 2
St-tions EEL.
VALTE AM MID VALVE SIZE VLV ACT POS.
TIfE 3EMI EEQ. EBQ.
ESQ.
ALT.
c'J :
IEEEER QASS COMD CATEGNY (im.) TYPE TYPE IM.
(sec.) FOS.
FUS. 1EST BK).
TEST RENARE3 0
C IR A-4 CIV j
2-PA-137 2
D-12 A-2 2
G H
C C
IR A-4 CIV 2-PA-1044 2
J-4 A-2 2
G H
C C
LR A-4 CIV 0-PSW-1020 D-9 A-2 3
G H
D-42 Rev. 1 9/26/88
]I u
iJl
.ll il1 8
18 S
./
3 ER v2 e/
AN R9 EE 1
.T T
TS E
LE E
A1 H
S LQD 1
0 EEN 8
mR MO CS C
C C
C C
Q C
Q C
C C
C C
C C
C Q
.T EE V
V V
V V
V V
V V
V V
V V
V V
V V
.O C
C C
C C
N D
Q5
/
/
/
O O
O
/
O O
O
/
O O
O O
O O
E0 O
O O
O O
I RF P
ES C
C C
C C
C C
C C
C C
C C
C C
C C
N DO NF
)
P EE c.
I e T (s 34 e
5D m
D t
0M s
FI y
S r
T a
w e
LF C
C C
C C
C C
C C
C C
C C
C C
C C
d VE e
VT F
T y
r
)
i Z n 6
6 6
6 6
6 6
6 4
4 4
6 4
4 4
4 2
E II l
i S(
xu A
r Vn 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
Ee Ln E
Au C
C C
C C
C C
C C
C C
C C
C C
C C
M VT A
A N
C M.
9 8
8 9
8 9
9 9
1 1
8 7
4 3
2 2
0 DM 7
1 1
E C
B B
C B
B F
E B
G H
H B
H C
G S
I M
H Y
PG S
5 A
3 3
3 3
3 3
3 3
2 2
3 3
3 3
2 2
3 t
S E
f5I AC 2
m 2
4 6
8 9
0 3
0 3
4 9
0 1
ER 0
3 6
8 J
1 1
2 2
3 8
9 9
9 9
0 0
O VE 1
0 0
0 1
1 1
1 1
1 1
1 1
1 1
2 2
N LB 1
1 1
1 i'
VU W
W W
W _W W W
W W
W W
W W
AM A
A A
A A
A A
A S
S S
S
.A I
N A
M M
M M
A A
A 2
2 2
2 2
2 2
2 2
2 2
2 2
2 2
2 2
N U
8 I8
/
E 6
E v2 E
e/
h R9 N
EE 1
.r T
Tr E
LE E
AT ES LQD 1
0 EEM 8
EE frO
.T QS Q
Q Q
T T
B1 V
F F
S S
E E1
.ON J
QS 0
O O
O O
EU I
EP P
n.
E5 C
C C
C C
o0 nP
)
0 0
m c.
1 8
ie 1
T (s 44
-D se sD X
X t
oM s
rI y
t tE r
cP A
A AY t
T a
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LP C
L L
V V
e VY G
G R
R T
T y
2 2
r
)
/
/
~
z.
i rm 2
6 6
1 1
t1 i
s(
l 1
1 xu A
Y sR yn 1
1 1
1 1
Ln E
aa C
B B
C C
M vT A
A N
C M
E D
T nE 0
9 8
1 1
S iD 1
1 1
B B
Y mOC H
3 D
S s
t s sa 3
3 3
3 3
e sl 2_
aC 2
0 1
1 2
Ea 0
7 7
0 0
O vs 2
0 0
5 5
N Le 4
4 4
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V V
V V
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2 2
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UNIT NO.
2 SYSTEM NAME: Auxillery Feedw tcr Syntes P&ID NO.
OM-801 SEET 1 _.
mL.
VALVE AEK IEID VALVE SIZE VLV ACT F05.
TIE NORM EEQ. ESQ.
EEQ.
ALT.
NUMNat CLASS mnen CAMG0r:7 (im.) TYPE TYPE IM.
(sec.) POS.
POS. Terr ND.
TEST RENNEES I!
2-CV-4520 3
B-6 B-1 6
GL A
X 19 0
O/C FQ 2-CV-4521 3
B-4 B-1 6
GL A
X 19 0
O/C FQ 2-CV-4522 3
D-4 B-1 6
GL A
X 19 0
O/C FQ 2-CV-4523 3
D-3 B-1 6
GL A
X 19 0
O/C FQ 2-CV-4530 3
H-5 B-1 6
GL A
X 19 O
O/C FQ 2-CV-4531 3
H-4 B-1 6
GL A
X 19 O
O/C FQ 2-CV-4532 3
F-4 B-1 6
GL A
X 19 0
O/C FQ 2-CV-4533 3
F-2 B-1 6
GL A
X 19 0
O/C FQ 2-CV-4550 3
H-7 B-1 6
GL A
X 90 0
O/C FQ
'l Rev. I D-45 9/26/88
Unit 2 RELIEF REQUEST NUMBER A-1 V-System:
Various P6ID:
Various Various valves which have actual stroke times of 2 seconds or less Valves:
Category: A and B Active I
Class:
Various Function: Various IWV-3413 to measure valve stroke time to Impractical Test Requirement:
the nearest second, and associated trending requirements of IWV-3417.
Valves with extremely short stroke times (less than 2 Basis for Re'11 eft seconds) have stroke times of such short duration that comparison of maasurements with previous data for specified percentage increases is not indicative of performance.
With mearurment of stroke degrading valve times to the nearest second per IWV-3413(b), a very small increase in stroke time will result in an extremely large percentage change, which could result in an unnecesssary increase in test frequency and challenges to valves.
Verification that valves meet a specified maximum stroke time of short duration provides adequate assurance of operability.
Only the maximum stroke time will be verified for Alternative Testing:
those valves with nominal stroke times less than 2 seconds.
The trending requirements of IWV-3417(a) will, therefore, not apply, i
l Rev. 1 D 46 9/26/88
Unit 2 RELIEF REQUEST NUMBER A-2
/
i System:
Various MID:
Various Valves:
Various solenoid actuated valves Catesory: A and B Active Class Various Impractical Test Requirement:
IWP-3300 requirement to locally verify remote position indication at least once avery 2 years.
Basis for Roliet's Relief Request Withdrawn I
Alternative Testing:
I 1
1 Rev. 1 D-47 9/26/88 1
Unit 2
,1 RELIEF REQUEST NUMBER A-3 l
}
Mystem:
As Required, Unit 2 P&ID:
Where Applicable Valves:
As Required Category: C Class:
As Required Function: Relief Protection on Various Systems IW-3512 requires compliance to ASME PTC Impractical Test Requirement:
25.3-1976.
Paragraph 3.02 of PTC 25.3 1977 Addendum, requires, "A
person who supervises the test shall have a formal education in thermodynamics and fluid mechanics.
In addition, he shall have at least two years practical axperience in fluid flow measurement and have had experience in test supervision."
Basis for Relief:
'Ite requirement of ASME PTC 25.3-1976 for the qualifications of a relief valve test supervisor are to a utility.
It would result in additional burdensome staff requirements that are not warranted in light of the alternate means of meeting the intent of this paragraph.
The Plant Operating Safety Review Lonunittee Alternative Requirements:
reviews all test procedures and any unacceptable of relief valve testing.
There are results typically several members of this committee that meet the educational and experience level requirements of the Code.
All test results are reviewed by the System Engineer respons!ble for the coeponents in the system the relief valve protects.
The personnel who conduct the tests meet specific qualification requirements in accordance with ANS1/ASME N45.2.6 - 1978.
All calibrated instruments used for testing are within the scope of the site Quality Assurance requirements.
Rev. 1 D-43 9/26/88
Unit 2 RELIEF RgQUKf,T NdMBER A-4 I
System:
Various P61D:
Various Valves:
All those identified with "CIV" in the Remarks column of the If associated Valve Test Program.
I i
Class Various l
Impractical Test Requirements:
a.
IWV-3421 through 3425 regarding leak rate test methodology.
b.
IWV-3427(b) regarding leak rate trending requirements.
I In keeping with NRC Staff position, all CIV testing Basis for Reliefs a.
shall be performed under 10CTR50 Apprendix J in addition to IWV-3426 and IWV-3427(a).
Testing per 10CTR50 Appendix J meets the intent of leak rate testing per Section XI, but will be controlled via the Local Leak Rate Testing Program, b.
The attached data shows that the variability of leak rates for valves 6 inches and larger is excessive.
CCNFP feels that this excessive variability shows the relative independence of one leak rate test to another.
The tendency towards random leak rate dcta would cause unnecessary testing per IWV-3427(b), with no identifiable increase in benefit to public health and safety.
The worth of performing this additional trending is also called into question by the recent ASME approval of OM-10
("Inservice Testing of Valves"), which is the planned replacement to Section XI testing rules. OM-10 does not require trending of valve leak rates.
Alternative Testimat a.
CCNPP shall test all CIVs under the requirements of 10CTR50 Appendix J, in addition to IWV-3426 and IWV-3427(a).
b.
CCNPP shall perform no alternative testing in keeping with OH-10 guidance.
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Rev. 1 D-49 9/26/88
Unit 2 RELIEF RE4143T NUMBER VS-1 System:
Ventilation System MID:
OM 65, SH 1 Valves:
2-CV-1410, 2-CV-1411, 2-CV-1412, 2-CV-1413 Category: A-1 Class:
2 Function: Containment Isolation IW-3400 requirement to stroke the valves Impractical Test Requirement:
quarterly These valses are normally locked shut with power removed.
Basis for Relief:
They are only required to stroke in Mode 6.
It is not desirable to stroke test these valves during each cold shute un since unnecessary stroking could cause degradation of *he valve's leak-tight capability.
This l
would result in an unnecessary increase in testing and valve maintenance.
The valves will be full stroke tested on a refueling Alternative Testina:
frequency.
Rev. 1 D-50 9/26/88
Unit 2 RELIEF REQUEST NUMBER RC-1 System:
Reactor Coolant P6ID:
OH-460 Valves:
2-ERV 402, 404 Category: C-1 Class:
1 Function: Relieve reactor coolant pressure.
Impractical Test Requirement:
Setpoint test per IW-3510.
These valves are categorized per Calvert Cliffs Technical Basis for Relief:
Specifications as ASME Section XI Category C-Active (relief valve).
However, due to the unique valve design, these valves cannot be tested per 1W-3510, since the valves are actuated as the result of an electric signal from a pressure measurement device.
Alternative Testias:
Valves are tssted per Technical Specifications at refueling intervals.
The test includes a channel calibration of the actuation channel.
A channel functional test.
excluding valve operation, is performed within 31 days prior to entering a condition when this valve is required t> serve as an MPT relief, and every 31 d,ays thereaf ter when the valves are required to be operable.
In addition, these valves will be functionally tested each cold shutdown prior to placing them in servico for Low Temperature Overpressurization Protection.
Rev. 1 D-51 9/26/88
Unit 2 REI.IEF REQUEST NUMBER SI-1 System Safety Injection and Containment Spray MID:
OM-462, Sh. 3 Valves:
SI-316, SI-326 El-330, SI-340 Category: AC-1 Class:
2 Containment Spray Header inlet checks, inside and outside Function: containment isolation valves.
Impractical Test Requirement: IW-3520 requirement to exercise the valves once every 3 months.
Check valves SI-316 SI-326, SI-330, and SI-340 cannot be Baals for Relief:
stroked during operation without spraying large quantities of contaminated water into the containment.
This contaminated refueling pool water is also borated to approximate'y 2300 ppm.
Spraying the containment would result in a radtocetive contamination cleanup problem and damage components such as lagging, reactor seriously coolant pumps, and control rod element assembly coils.
One valve will be disassembled at each refueling Alternative Testing:
outage to inspect the valve's internal components.
If degradation is found that would result in the valve being unable to pass full design flow, then all valves will be inspected in the same refueling outage.
Rev. 1 D-52 9/26/88
Unit 2 RELIEF MSUEST NUMBER SI-2 System:
Safety Injection and Containment Spray MID:
OH 462, Sh. 3 Valves:
SI-4148, SI-4149 Category: C-1 Class:
2 Function: Containment Sump outlet Check Valves IW-3520 requirement to exercise valves once Impractical Test Requirement: every 3 months.
These check valves cannot be full stroke exercised without Basis for Relief flooding the containment floor with contaminated refueling i
pool water that is borated to approximately 2300 ppm.
l This would result in serious damage to lagging and in eddition to the electrical systems control components radioactive contamination cleanup problem of the containment sump and associated uguipment.
One valve will be disassembled at each refueling i
Alternative Testing:
outage to inspect the valvo interns 1 components.
If degradation is found that would result in the valve being unable to pass full design flov, then all valves will be inspected in the same refueling outage.
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I Rev. 1 1
D-53 9/26/88
Unit 2 l
REI.IEF REQUEST NUMBER SI-3 System:
Safety Injection F61D:
OH-452, Sh. 2 Valves:
2-S1-215, 2-SI-225, 2-SI 235, 2-SI-245 l
Category: AC-1 Class:
1 Peaction: Safety Injection Tank discharge check valves, pressure system isolation valves Impractical Test Requirement: IW-3520 requirement to full-stroke exercise valves.
It is not possible to measure the flowrate through these Basis for Relief:
valves nor to simulate rapid depressurization of the RCS.
Additionally, achieving the design flowrate through t'sese i
valves would require removal of the reactor vessel head and the flowrate required could cause damage to the core I
f internals.
One valve will be disassembled at each refueling Alternative Testina outage to inspect the valve's internal components.
If degradation is found that would result in the valve being unable to pass full design flow, then all valves will be inspected in the same refueling outage.
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Rev. 1 0-54 j
9/26/88
Unit 2 RELIEF REQUEST NUMBER SI-4 System:
Safety Injection P61D OM-462, Sh. 2 Valvest 2-SI 217, 2-SI-227, 2 S1-237, 2-SI-247 Category: AC 1 Class:
1 Safety Injection to RCS loop check valves, pressure isolation valves Function:
IVV-3400 requirement to test the valves' Impractical Test Requirement: pressurn isolation function.
Basis for Relief:
The pressure upstream of these valves is continuously and an increase results in an alarm in the monitored, control room, which requires operator action in accordance with the Calvert Cliffs alarm manual.
This manual vould require the operator to determine the leakage rate through these valves.
Pressure upstream of these valves is continuously Alternative Testina:
monitored and an increase will be alarmed in the control room.
This continuous monitoring provides assurance that these valves are meeting their pressure isolation safety function.
Rev. 1 D-55 9/;6/88
Unit 2 RELIEF REQUEST NUMBER SI-5 l
System:
Safety Injection P61D:
OM-462, Sh. 2 I
2-SI-217, 2-S1-227, 2-S1-237, 2-SI-247 Valves:
Category: AC-1 Class:
1 Safety Injection to RCS loop check valves, pressure isolation valves Function:
IWV-3520 requirement to full-stroke exe cise the Impractical Test Enquirement: valves.
It is not possible to measure the flowrate through these valves nor to simulate rapid depressurization of the RCS.
Basis for Relief Additionally, achieving the design flowrato through these valves would require a removal of the reactor vessel head and the fivwrate required could cause damage to the core internals.
The valves are part stroked whenever shutdown cooling Alternative Testing:
One valve will be disassembled at is in operation.
each refueling outage to inspect the valve's internal If degradation is found that would components.
in the valve being unable to pass full design result then all valves will be inspected in the same
- flow, refueling outage.
Rev. 1 D-56 9/26/88
Unit 2 l-l RELIEF REQUEST NUMBgR SI-6 System:
Safety injection F61D:
M-<62 Valves:
2-51-4146, 2-SI-4147 Catesory: C Class:
2 Refueling Water Tank Outlet Check Valves Function:
Impractical Test Requireennt: IW-3520 requires a check valve to be tested to its design flow position once a quarter.
Basis for Relief:
It is not possible to provide full design flow through these check valves during any period of plant operation.
The full design flow would require the simultaneous operation of I LPSI pump, 1 CS pump, and 1 HPSI pump for each valve with the combined discharge path that l
duplicates the design basis LOCA.
It is not possible to provide simultaneous full design flow from all three pumps due to core damage from excessive reactor vessel flow and deluging of containment interior components from the spray header.
These valves will be part stroke tested once l
Alternative Requirement:
One valve will be disassembled at per quarter.
each refueling outage to inspect the valves internal components.
If degradation is found that would result in the valve being unable to pass full design flow, then all valve will be inspected in the same refueling outage.
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Rev. 1 D-57 l
9/26/88
Unit 2 RELIEF REQUEST NUMBER SI-7 1
t-System Containment Spray MID:
M 462 i
Valvest
'2-51-313, 2-54-323 A
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Category: C Class:
2 Functioat Containment Spray Pump Discharge Check Valve I-.
1 1
/
1WV-3520 requires a check valve to be tested to Impractical Test Requirement: its design flow positieti once a quarter.
l These valves cannot be full-flow stroke tested due to Basis for Relieft limitations on the bypass discharge flow paths.
The valves can be full flow tested only during refueling l
j outages where plant conditions can be established to allow the use of both containment spray pumps as alternate LPS1 1
pumps to provide Shutdown Cooling flow.
The Core Decay 1
t Heat Load is minimal and the need for a boration flow path dependent only on one charging pump occurs during refueling outages only.
i I
On a COLD SHUTDOWN basis, the valves will be Alternative Requirementt part-stroke tested. The valves will be Full Stroked each refueling outage during the Large l!
Flow testing of the respective containment spray pumps.
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Rev. 1 D-58 9/26/88
I APPENDIX E VAtNES TESTED DURING C01.D SIN'N Rev. 1 9/26/88
APPENDIX E VALVES 'IT.STEDlURI_NG COID SHlTn]OWN System Unit Valve Number Justification Main steam &
1/2 1-CV-4043 Valves cannot be full stroke l
1-CV-4048 tested during plant 2-CV-4043 operation without causing i
Reheat 2-CV-4048 major plant transients / plant j
shutdown. Valves are part-l i
stroked per manufacturers recommendations only.
l Valves are full stroke j
tested it Cold Shutdown at 3 month intervals as allowed by Section XI.
Exercising these f.or:. elly Condensate &
1/2 1-FW-130 1-TV-133 open valves would recuire a Teedwater cessation of feedwater tlow 1-MOV-4516 1-MOV-4517 to the steam generator.
i This would cause transients 2-TV-130 l
2-TV 133 leading to shutdown. Valve l
2-MOV-4516 logic and system configura-2-MOV-4517 tion prevent any part-stroke testing of MOVs. Therefore, l
the valves are full stroke tested at Cold Shutiown at 3 month intervals as allowed by Section XI.
Service Water 1/2 1-SRV-323 Exercising these valves 1-SRV-324 during operation would Cooling System stop cooling water flow to 1 SRV-325 the main turbine auxiliaries 1-CV-1500 1-CV-1637 and other vital secondary 1-CV-1638 plant equipment necessary 1-CV-1639 for power operation, 2-SRV-323 causing plant shutdown.
2-SRV-324 System configuration 2 SRV-325 prevents Air Operated Valvo 2-CV-1600 part stroke testing during 2-CV-1637 power operation. Valves are 2-CV-1638 full stroke exercised at i
Cold Shutdown at 3 month 2-CV-1639 intervals as allowed by Section XI.
Rev. 1 E-1 9/26/88 l
System pait Valle Number Justif[ cation i
Component Cooling 1/2 1-CV-3832 Exercising these valves t-CV 3833 during operation would stop cooling water flow 2-CV 3832 to the reactor coolant 2 CV-3833 pumps and other vital equipment necessary for power operation causing equipment damage or plant shutdown. Valve logic pre-vents part-stroke testing of Air Operated Valves during power operation.
Valves are full stroke exercised at Cold Shutdown at 3 month intervals as allowed by Section XI Compressed Air 1/2 1 IA-337 Exercising these valves l
Plant &
1-MOV-2080 requires isolating 2-IA-175 instrument air to the Instrument 2-MOV-2080 containment thereby failing numerous air operated valves.
Although control of I
these valves is not required during an accident it is required for normal reactor i
operation.
System config-
'i uration and valve logic prevents part stroke testing these valves during power operation. Therefore, these valves are full stroke exercised at Cold Shutdown at 3 month intervals as allowed by Section XI.
Ventilation 1/2 1-HP 6900 Valves are required by Tech.
1-HP 6901 Spec to be saintained System 2-HP 6900 closed during Power 2-HP-6901 Operation. Valves are full stroke exercised at Cold l
Shutdown at 3 month intervals as allowed by Section XI.
l Rev.
E2 9/26/88 t
System Unit Valve _Nupber Justification l
Reactor Coolant 1/2 1-SV-103 Stroking valves during 1-SV-104 plant operation could cause System failure to resent properly 1-SV-105 1-SV-106 thus reducing plant 2 SV-103 reliability. Failure to 2-SV-104 reseat could cause system /
l' 2 SV-10$
equipment damage, therefore no full or part-stroking of l
2-SV-106 valves is possible. Valves are full stroke exercised at Cold Shutdown at 3 month intervals as allowed by Section XI.
CVCS 1/2 1 CVC-162 Valves cartnot be stroked l*
f 1 CVC-184 during operation without 1 CVC-435 stopping all charging 2 CVC-162 pumps. This would place 2 CVC-184 excessive thermal cycles l
2-CVC 435 on system equipment due to starting and stopping i
I charging and letdown.
l Therefore, valves are full stroke exercised at Cold 1
Shutdown at 3 month l
intervals as allowed by Section XI.
Exercising these valves CVCS 1/2 1-CVC 228 1-CVC 235 requires injecting concen-trated boric acid directly 2-CVC-228 into the reactor coolant 2 CVC-235 The resulting rapid system.
power decrease and reactor water chemistry change would cause plant shutdown. Flow
- !I is verified by measuring tank level change or flow l
through the changing pumps I
which is not possible during power operation. Therefore, the valves are full stroke l
exercised at Cold Shutdown at 3 month intervals as allowed by Section XI.
3 I
Rev. 1 i
E-3 9/26/88 l
I System Matt Valve humber Justificat[on CVCS 1/2 1-MOV 501 Valves cannot be stroked 1-CV+515 during operation without 1 CV-516 stopping all charging pumps.
2-MOV 501 This would place excessive 2-CV-515 cycles on starting and 2-CV-516 stopping charging and -
letdown which are required to optrate. This would also placo unnecessary cycles on a limited cycle life Regen.
Heat Exchanger, decreasing conpor.ent available i
lifetime. Therefore, valves l
are full stroke exercised at j
Cold Shutdovn at 3 month i
intervals as allowed by l
Section XI.
CVCS 1/2 1 CV 517 Velves cannot be stroked 1-CVC-185 (open) during plant operation due 2-CV 517 to the resultant thermal i
2-CVC-185 (open) stress to the spray line and spray nozzle. Valves will l
be full stroke exerr,ised at I
Cold Shutdown at 3 nanth i
intervals as allowed by Section XI.
i CVCS 1/2 1 CVC-185 (shut)
Exe'rcising these valves 1 CVC 186 (shut) requires personnel access 1-CVC 187 (shut) to high radiation areas 2 CVC-185 (shut) within the containment 2 CVC-18s (shut) during plant operation.
2 CVC 1f.7 (shut)
Man rei exposure, if the vdives vere stroked du-ing operation would be greater than 100 arem gamma and 50 mrem neutron. Therefore, the valves are full stroke exercised at Cold Shutdown at 5 month intervals as allowed by Section XI.
Rev. 1 E4 9/26/88
Justification gy.st e m Unit Valve Numby CVCS 1/2 1 CVC-505 Valves cannot be stroked 1-CVC 506 during plant operation 2-CVC-505 without stopping RCP seal 2-CVC-506 bleed off flow reducing RCP seal reliability, causing possible RCP failure. Valve
)ogic prevents part stroking these valves during power o;srations. Valves are full stroke tested at Cold Shutdown at 3 month intervals as allowed by Section XI.
l Safety Injection 1/2 1 SI-434 Valves cannot be full or Containment Spray 1-SI-446 part-stroked during 2-SI-434 operation because normal RCS l
System 2 SI-446 pressu;e is above the shut-off head of the I. PSI pumps.
l This would require depressurizing the reactor coolant system, causing plac.t shutdown. Valves will j
be full stroke exercised at l
Cold Shutdown at 3 month l
intervals an ellowed by I
Section XI.
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Safety Injection 1/2 1-S1-401 Valves canaot be full-i containment Spray 1-SI-405 stroked during power opera-1 31-410 tion because normal RCS
{
System 1-SI-414 pressure is above the shut-1 SI 427 off head of the HPSI pumps, 2 SI 401 Depressurizing the reactor 2.S1 405 coolant system would be 2-51-410 required, forcing plant 2 51-414 shutdown. Valves would be 2-SI-427 part stroked whenever the associated HPSI pumps are run to fill Safety Injection Tanks. The valves are full stroke exercised at Cold Shutdown at 3 month intervals as allowed by Section XI.
l Rnv. 1 E-5 l
9/26/88
System Mrtl Valve Numkn Just_i f icat ion i
Safety Injection 1/2 1 S1 118 Valves cannot be full Containment Spray 1-SI-128 stroked during operation 1 SI-138 because RCS pressure is System above shutoff head of the 1-51-148 2-51 118 HPSI pumps. Valves will be 2 SI-128 part-stroked whenever the SI 2 SI 138 tanks are filled and full-2 51 148 stroked at Cold Shutdown at l
3 month intervals as allowed by Section XI. The test conditions are established to prevent Low Temperature l
Overpressurization.
l Safety Injection 1/2 1 SI-114 Valves cannot be stroke Containment Spray 1 SI-124 tested during poser 1-SI 134 operation due to the head of l
System the LPSI pumps being less 1 SI-144 2-SI 114 than the required pressure 2-SI-124 to overcome the effect of 2 SI-134 Safety Injection Tanks Pres-2-SI-144 sure on these valvas.
l Valves will be full stroke I
exercised at Cold Shutdown i
i i
at 3 month intervals as I
l allowed by Section XI.
l Safety Injection 1/2 1 81-313 Valves cannot be stroke Containment Spray 1.S1 323 tested during power opera-l 2 51 313 tion as this may cause System borated water to deluge the 2-51-323 containment resulting in equipment damage and plant shutdown.
See Relief
,r Request SI-7.
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Safety injection 1/2 1-HOV 651 Valves are interlocked on l
~
Containment Spray 1 HOV 652 reactor coolant system 2-HOV-651 pressure and cannot be 2 HOV-652 tested at power. This is to l,
System provide overpressure protec-l':I tion of the downstream piping. The valves are full
'[
stroke exercised at Cold Shutdown at 3 month r
intervals as allowed by l
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Section XI.
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Rev. 1 l
E-6 9/26/88 i
r
System Unit yajye Number Justification Safety Injection 1/2 1-MOV 659 Failure of these valves in Containment Spray 1-MOV-660 the closed position during 2-MOV 639 operation would cause an System 2-MOV 660 entire safety system to become inoperable.
Valve logic prevents a part-stroke of these valves.
Therefore, these valves will be full-stroke exercised at Cold Shutdown as allowed by Section XI.
Auxiliary Feed-1/2 1-AFV 102 Exercising thwse valves full 1 AFV-116 or part-stroke during plant water System 1 AFV 129 operation would require 1-AFV-130 feeding hot steam generators 1-AFV-183 with cold feedwater thereby 1-AFW-190 thermally shocking the 1-AFV-193 auxiliary feedwater ring 1-AFW 194 within the steam generator.
i 1-ATW-199 Therefore the valves art
(
1-ATV-200 full stroke exercised at 2-AFW-102 Cold Shutdown at 3 month 2-AFV-116 intervals as allowed by 2-AFV-129 Section XI.
2-AFW-130 2-AFV-183 2 AFV-l';;
2-Arg.;93 i* AIV* 19 4 2 - AFV 199 2-ATV 200 Auxiliary Feed.
1/2 1-MS 103 (shut)
Testing these valves during 1-MS-106 (shut) power operation requires water System 2 MS-103 (shut) filling the downstream pipe 2-MS 106 (shut) with water.
Pump damage could occur if the pumps were started in this I
configuration. Therefore, the valves are tested cicced at Cold Shutdowns only, as allowed by Section XI.
Rev. 1 E-7 9/26/88 l
L
System ynit Valve Number Justifica11pn l
Auxiliary Feed-1/2 1 MS-103 (open)
Full stroking these valves water System 1-MS-106 (open) during power operation j
1-MS-108 would require feeding hot 1-MS-110 steam generators with cold 2 MS 103 (open) feedwater thereby thermally 2+MS-106 (open) shocking the ATV ring within 2 MS-108 the S/G.
Therefore, the 2-MS-110 valves will be part stroked quarterly during power operation and full stroked l
at Cold Shutdown as allowed by Section XI.
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Rev. 1 l
E-8 9/26/88 l
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l APPENDIX F DRAVIN3S USED IN PREPARATION 1
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APPE:iDIX T DRAVINGS USF.D IN PREPARATION Drawing Revision /
Sheet No.
Stit No.
Date Ijtje i
1 OH-35 18/2-20 85 Main Steam & Reheat OH 36 20/6 5-85 Hain Steam & Reheat 1
2 4
1 OM 39 5/7-1 86 Condensate & Teedwater OM 40 5/8 20-86 Condensate & Feedwater 4
2 DM 46 12/8 8 86 Service Water Cooling 1
1 OM 46 14/8 8 86 Service Water Cooling 2
1 OM-47 10/3-13 86 Service Vater Cooling i
2 OM-47 12/8 8 86 Service Vater Cooling 2
2 s
OM 49 17/7-1-86 Circulating Salt Vater 1
1 Cooling OM 49 9/12-17-86 Circulating Salt Water 2
1 Cooling 1
1 OM-51 16/7-30 86 Component Cooling System 2
1 OM 51 5/7 2 86 Component Cooling System 3
1 OM 51 8/6 16-86 Component Cooling System OM-52 7/10 16-84 Containment Charcoal ritter 1
1 Spray OM 53 14/8-19 86 Compressed Air:
Instrueep 1
1 and Plant OM-53 3/3-7-85 Compressed Air:
Instrament 2
1 and Plant OM 53 10/8-19 86 Conpressed Air:
Instrument 3
1 and Plant OM-53 1/3-26 85 Coapressed Air:
Instrument 4
1 and Plant 2
162 OM-56 5/11-15 85 Plant Fire Protection Rev. 1 F-1 9/26/88
Drawing Revision /
Fo, Date Title S h e e t __No.
pg[1 OM 58 16/10-23 86 Spent Fuel Pool Cooling &
1 162 Pool Till and Drain OM 59 19/11 6 86 Vell Vatst, Pretreated 1
1&2 Vater, Demineralized Vater, and Condensate Storate OM 65 12/1-4-85 Ventilation 1
162 OM-65 12/12-11 85 Ventilation 2
152 OM 65 5/10 4 84 Ventilation 3
162 OM 65 7/9 3-86 Ventilation 4
1&2 OM 66 20/7-7-86 Reactor Coolant and Vaste 1
162 Process Sample l
OM-66 6/2 21-86 Reactor Coolant and Wasta 3
162 Process Sample OM 68 10/1-21-86 Nitrogen 02nerating &
1 162 Blanketing OH 71 4/13 23 84 Plant Heating 2
162 OM-72 23/*-11-86 Reactor Coolant 1
1 OM-72 OA/7 31-86 Reactor Coolant 2
1 OM-73 31/11 21 86 Chemical & Volume Control 1
1 OM 73 13/8 25 86 Chemical & Volume Control 2
1 OM 73 13/4-14 86 Chemical & Volume Control 3
1 OM 74 26/5-9 86 Safety Injection 6 1
1 Containment Spray OM 74 7/5-20-85 Safety Injection &
2 1
Containment Spray OM-74 4/5 1-85 Safety Injection &
3 1
Containment Spray OM 76 9/6-19 85 Vaste Process Equipment 1
1
& Area Drains i
OM-76 12/4 17 86 Vaste Process Equipment 2
1
& Area Drains Rev. 1 F-2 9/26/88 i
1
Drawing Revision /
No.
Date Title Sheet No.
Unit OM-76 13/5-20-(*
Waste Process Equipment 3
1
& Area Drains OH-76 1/4 Waste Process Equipment 4
1
& Area Drains OH-77 13/
Rsactor Coolant Waste 1
1&2 Processing OH-77 8/5-12-86 Reactor Coolant Waste 3
1&2 Processing l
OM-78 20/8-8-86 Waste Gas & Misc. Waste 1
162 l
Processing OH-78 8/8-8-86 Waste Gas & Hisc. Waste 2
1&2 Processing OM-98 16/7-7-86 Area & Process Radiation 1
162 Monitoring OH-115 10/4-28-86 Chemical Addition &
1 1&2 Condenser Tube Bulleting OH-115 4/1-6-86 Chemical Addition &
2 1&2 Condenser Tube Bulleting OH-115 3/7-7-86 Chemical Addition &
3 162 Condenser Tube Bulleting OH-450 13/10-31-86 Circulating Water Cooling 1
2 l
OH-450 16/12-20 8S Circulating Water Cooling 2
2 OH-452 16/1-23-86 Component Cooling 1
2 OH-452 1/10-8+64 Component Cooling 2
2 3
2 OM-452 8/6-16-86 Component Cooling 1
OH-453 7/4-28-86 Containmens Charcoal 1
2 l
Filtor Water Spray' OM-454 12/1-8-86 Compressed Air:
Instrument 1
2 and Plant OH-454 4/10-10-86 Compressed Air:
Instrument 2
2 and Plant OM-454 16/10-30-86 Compressed Air:
Instrument 3
2 and Plant Rev. 1 F-3 9/26/88 L
Drawing Revision /
No.
Date Title Sheet No.
Unit 4
2 OM-454 2/3-3-86 Compressed Air:
Instrument and Plant OH-460 18/1-30-86 Reactor Coolant 1
2 OM-460 OA/10-9-86 Reactor Coolant 2
2 OM-451 25/7-2-86 Chemical & Volume Control 1
2 OH-461 3/12-17-84 Chemical & Volume Control 2
2 OH-461 8/5-12-86 Chemical & Volume Control 3
2 OM-462 26/8-13-86 Safety Injection &
1 2
Containment Spray Od-462 6/3-11-86 Safety Injection &
2 2
Containment Spray OM-462 3/12-10-84 Safety Injection &
3 2
Containment Spray OH-463 8/3-10-86 Gas Analyzing 1
162 2
' i2 OH-463 5/8-5-86 Gas Analyzing OH-464 12/7-7-86 Steam Generator Blowdown 1
1 Recovery OM-465 12/4-21-86 Steam Generator Blowdown 1
2 I
Recovery 1
162 OM-479 15/10-9-86 Plant Water & Air Service OM-479 7/3-28-86 Plant Water & Air Service 2
162 OH-800 10/10-16-86 Auxiliary Feedwater 1
1 OH-801 10/9-29-86 Auxiliary Feedwater 1
2 l
F-4 Rev. 1 9/26/88
APPENDIX G CALVERT CLIFFS NUCLEAR POWER PIMr UNITS 1 AND 2 1
FIRST TEN YEAR PUMP AND VALVE INSERVICE INSPECTION PLANS WITil INCORPORATED PAGES FROM JANUARY 30, 1981 REVISED PROGRAM
\\
l 1
l l
l Rev. 1 9/26/88 l _ _ __ _ ___ _.
APPENDIX H CHRONOLOGY OF SUBMITTALS AND SELECTED DOCUMENTATION 1
l CHRONOLOGY OF SUBMITTALS l
l Rev. 1 9/26/88
l Calvert Cliffs Nuclear Power Plant Unit 2; Pump and Valve Inservice 1.
Inspection Program - May 1, 1980 - Mr. A. E. Lundvall, Jr. to Mr. R. W. Reid (see Appendix G) 2.
Calvert Cliffs Nuclear Power Plant Unit 1; Pump and Valve Inservice Inspection Program - May 9, 1980 - Mr. A. E. Lundvall, Jr. to Mr. R. W. Reid (see Appendix G) 3.
BG6E Co. - Inservice Valve Testing Program Relief Request - December 24, 1980 4.
Pump and Valve Testing (revised pages) - January 30, 1981 - L. B. Russell to Mr. A. E. Lundvall, Jr.
5.
Calvert Cliffs Nuclear Power Plant Units 1 & 2; Inservice Inspection and Pump and Valve Programs Request for Relief from ASME Code Section XI Requirements Determined to be Impractical - November 6, 1981 -
Mr. A. E. Lundvall to Mr. Robert A. Clark 6.
US NRC - Safety Evaluation Granting Relief from ASME Code Section XI February 8, 1982 - Mr. Robert A. Clark Inservice Testing Requirements to Mr. A. E. Lundvall 7.
Calvert Cliffs Nuclear Power Plant Units 1 & 2; Inservice Inspection Program - July 22, 1982 - Mr. A. E. Lundvall to Mr. Robert A. Clark 8.
Calvert Cliffs Nuclear Power Plant Units 1 & 2; Inservice Inspection and Pump and Valve Programs Request for Relief from ASHE Code Section XI Requirements Determined to be Impractical - August 30, 1982 -
Mr. A. E. Lundvall to Mr. Robert A. Clark 9.
US NRC - Safety Evaluation and Federal Register Notice - December 22, 1982 - Mr. Robert A. Clark to Mr. A. Lundvall 10.
Calvert Cliffs Nuclear Power Plant Units 1 and 2; Inservice Test Program July 11, 1985 Request for relief from ASME
- codes,Section XI requirements, determined to be impractical - Mr. A. E. Lundvall to Mr. James R. Miller 11.
U.S. NRC - Request for Additional Information - Proposed Pump and Valve Inservice Testing Program - November 13, 1987 12.
U.S. NRC - Request for Additional Information - Proposed Pump and Valve Inservice Test Program - April 19, 1988 -
Mr. S. McNeil to Mr. J. A. Tiernan 13.
Calvert Cliffs Nuclear Power Plant Units 1 and 2 Relief Request for Section XI of ASME Code - March 30, 1988 - Mr. J. A. Tiernan to U.S. NRC Document Control Desk 14.
Calvert Cliffs Nuclear Power Plant Units 1 and 2 Proposed Pump and Valve Mr.
J.
A. Tiernan to U.S.
NRC July 5, 1988 Inservice Test Program Document Control Desk 15.
U.S. NRC - Request for additional Information - Proposed Pump and Valve Mr.
S. McNeil to Mr. J. A.
Inservice Testing Program - August 9, 1988 Tiernan Rev. 1 9/26/88
___