ML20205P461
| ML20205P461 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/31/1986 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20205P444 | List: |
| References | |
| PROC-861231, NUDOCS 8704030282 | |
| Download: ML20205P461 (150) | |
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9 CALVERT CLIFFS NUCLEAR POWER PLANT BALTIMORE CAS & ELECTRIC COMPANY ASME SECTION XI PUMP AND VALVE TEST PROGRAMS - UNITS 1 'AND 2 SECOND TEN-YEAR INTERVAL 8704030282 870226 PDR ADOCK 05000317 PDR op
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. TABLE OF. CONTENTS I
EECTION IHLE RAGE I
1.0 INTRODUCTION
Relationship with Technical Speciftsations . .. .. 1.
11 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 Multiple Reference Values . . . . . . . .... .. ,
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- 3. 0, , VALVE INSERVICE TEST PROGRAM . ....... . . . .. ..
Category A Valves ................. 3 3.1 Pressure Isolation Valves . . . . . . . . . .. .. 3 j 32 4
3.3 Tharmal Relief Valves ...............
3.4 Cold shutdown Testing ............... 5 3.5 Part-stroke Testing .... . . . . . . . . ... . 5
.. .............. 6 36 Fail-Safe Actuators 3.7 Valve Timing and Remote Indication . . . .. .... 6 3.8 Passive Valves . .................. 6 3.9 Stroke Times . ................... 6 3 10 Shut Down Cooling Valves . . . .. . . . . . .... 6 3 11 Post-Maintenance Testing . . . ... . . .. .... 6 3.12 Relief Valve Testing . ............... 7 APPENDIX A UNITS 1 AND 2 PUMP TESTINC PROGRAM APPENDIX B LEGEND FOR VALVE TESTING PROGRAM APPENDIX C UNIT 1 YALVE TEST 1NC PROGRAM APPENDIX D UNIT 2 VALVE TESTING PROCRAM APPENDIX E VALVES TESTED DURING COLD SHUTDOWN APPENDIX F DRAWINGS USED IN PREPARATION APPENDIX C PREVIOUS TEST PROGRAMS APPENDIX H DOCUMENTATION AND CHRONOLOGY OF SUBMITTALS l
1 1 Rev. O. 12/31/86 l
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USERVICE TITTIgr, FROGRAM POR (' ? M 1 b N '
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CALVERT CLIFFS hUCI. EAR POWER PLANT UNITS 1 AND 2 j, .m i[ l i
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1.0 INTRODUCTION
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( i Under the provisions of 10CTR50.55a dn'aervice testing of safttp r neted pumps and valves will be perfyrmed in accordpnce with,Section II oslcheMSU2 , f Boiler and Pressure Yessel Code and appl! cable, addends. As specified in >
10CFR50.55a(b), the ef f ective edition of Seca ton XI with regard 'to 'this progin .g 1s the 1983 Edition thrc, ugh the Sumrer 1983 Addenda. ' This p'ecisram identifies the i N.?
pump and valve inservice t estir.g thet will be perforswd ~ati tha Calvert Cliffs Nuclear Power Plant Units 1 and 2 to comply wi$h the;recluirsements of 10CFR50.55a.
t This program applies to the Second ten Year Inservice Inspection Interval , ,
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beginning April 1, 1987 { ,
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The ASME Section XI Pump and Valve ' est Progra n is requird by Calvert, y' Clif f s Nuclear Power Plant Technical Specification 4.0.5 as avellt as 10CTR5G. ,
Based on Technical Specification reqairements, in the event of any conflict's between ASME Section XI requirements and the,tequirements,of it:hnical t<
Specifications, the plant Technical Specifica11ons snall govern. Since Calvert '.
Cliffs may be updating its Refueling Cycle to 24 months, ASME_Section XI r
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requirements tied to the time interval of 2 years, will be tested furing each 4 refueling.
1'l sy 3^ l 1.2 on=1ifIcation of Tast_Earsonnel -
Personnel performing pump and valve testing per ASME Section.XI 56bsections IWP and IWV will be qualified in accordance bith the Calvert Cliffs QdalitJ s Assurance Program. This is in keeting with th( requirements of ASME Section XIf ' '
as clarified by ASME Code Interpretation XI-1-82-06R. , '
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I 20 PUMP INSERVICE TESTING P10GP.AY /i m e
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The pump test program shall be conducted gin accordance with SubsectioMWPi of Section XI of the 1983 Edition of the ASME Loller and Pressurt VesJe1 C M e throughSummer1983 Addenda,exceptforreliefrequestedundertheproilsionsh* I 10CTR50.55a(g) (5) (iii). Appendir A details'.the Inservice [% sting program for T all safety related pumps at Calvett' Cliffs Nucle'ar Pcwer Pleit Units 1 and 2.
These tables list each pt.mp required to be ' ested t 'in accordsice 'with IWP-1100 of Section XI of the Code. Each parameter to be measured. as well as specific '/ l relief requests concerning r.on-conformance, are also'l uted.
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Subsection IWP-3300 requires pump bearing temperatures be measured at least y.
( / t"sonce each year. Industry experience demonstrates that bearing temperatures ;
f' I tynically rise only minutes prior to failure. Any bearing failure predicted by a l waar1x recording of bearing temperature would be a random event and thus, gaarly meewarement of bearing temperatures does not increase the level of confidence in
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composent reliability. The expense of adding the additional. testing both in justified.
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? component degradation and man-hours expended is, therefore, not a i S g j Further, IWP-3500(b) specifies that pumps be run until bes.rftg temperatures Clearly
! y stabilizs as determined by three measurements at 10 minute intervals.
- a the pump would have to be run in excess of one-half hour to obtain these readings. The pump degradation caused by this requirement does not justify the
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Vibration data taken on at least a quarterly basis will be used to define f s pump mechanical condition. This request for relief should apply for all bearings presently required to be temperature tested. .
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2.2 Pu=a Testine Rangas
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Calvert Cliffs will revise the upper boundary for Alert and Act' ion ranges of differential pressure and flow for selected pumps. This position reflects the opproved relief request from the first ten year program and meets with ASME Code V.vguirements per IWP-3210. Pump performance will be adequately evaluated using upper differential pressure or flow range limits of 1.05 and 1.07 (times delta P/
flow reference, as appropriate) for the Alert and Action ranges respectively.
Normal operation of the pumps in these ranges will still meet their required safety function. As identified in the first ten year testing program NRC safety evaluation, "Small positive increases in observed delta P are most likely not significant with regard to centrifugal pumps. More over, such factors as instrument uncertainty, water density, and instrument error might lead to Based on the above, these spurious actuation of alert and action ranges."
reduced range limits are felt to meet the intent and requirements of ASME Section XI.
2.3 Imergancy Dianal Evnta==
The inservice operability testing of pumps (and valves) associated with the Emergency Diesels, including the Diesel Oil Transfer System, are excluded from the enclosed test programs. These components are considered an integral part of least monthly per the Emergency Diesel System and are functionally tested at Techr;ical Specifications. Thus, the functional operability 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 meet its functional requirements. Calvert Cliffs Technical l
~ Specifications and plant maintenance schedules together provide assurance of operability as well as information concerning equipment degradation over time.
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,l 2,.4. thaltip1M toferem.e values Based on plant operating conditions tand pump testing hydraulic circuit, i Calvert Cliffs may choose to generate multiple sets of. reference values (per IWP- l 3112) in order to more fully describe pump hydraulic condition. Each set of pump l reference values will meet'all appropriate requirements of IWP-3000. '
l 3.0 VAL 7E INSERVICE TESTING PROGRAM
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l The valve test program for Calvert Cliffs Nuclear Power Plant Units 1 and 2 '
shall be conducted in accordance with Subsection IWV of Section XI of the 1983 Edition of the ASME Boiler and Pressure Vessel Code through the Summer 1983 l Addenda, except for relief requested under the provisions of 10CFR50.55a(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. '
I 3.1 Cairgnry A Valvem )
Valves for which seat leakage is important may generally be classified as pressure system isolation valves (PSIV), containment isolation valves (CIV), or both pressure and containment isolation valves. Containment isolation valves falling within the scope of ASME 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 - a The Calvert Cliffs Nuclear Power Plant Units 1 and 2 were designed to perform the Appendix J, Type C tests, not the individual Category A leak test (i.e., some
. penetration test connections test more than one valve at a time). Accordingly, all CIV seat leak testing shall be performed in accordance with the requirements l of 10CFR50, Appendix J. Type C, in lieu of the Category A requirements of Section I XI. l All CIVs have been categorized as A-Active or A-Passive, and will, as a minimum, be leak tested per 10CFR50 Appendix J. Passive valves will in general have no other testing performed. Valves 1-CVC-103 and 1-CVC-105 in the Reactor Coolant Letdown Line (P&ID OH-73) have been analyzed 63 ;assively open, however, a leak test will be performed per Appendix J at rib 314 n. intervals. Valves 1-CV-518 and 1-CV-519 are also leak tested, even ch<e,4 : valves fail open upon loss of power. A similar situation exists on U.S. 2 3.2 Erasrure Tanlation valves The purpose of the Pressure System Isolation Valves (PSIV's) is to reduce the possibility of an ih.er-system LOCA which would pressurize low pressure i systems to pressures exceeding their design limits.
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' . . At.Calvert . Cliffs Nuclear. Power Plant Units 1 and 2. the following PSIV's
" ' are' leak tested:
SI-148 (SI header check) J SI-217 (llA loop inlet check)
SI-227 (118 loop inlet check) ,
SI-237 (12A loop inlet check) I SI-247 (128 loop inlet check)
SI-215 (llA SI tank outlet check)
SI-225 (llB SI tank outlet check)
SI-235 (12A SI tank outlet check)
SI-245 (12B SI tank outlet check)
Valves SI-ll8, SI-128, SI-138, and SI-148 isolate the Safety Injection Headers (LPSI and HPSI) from the Safety Injection Tank discharges. These valves are individually leak tested in accordance 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 outlet valves displayed in the control room. Using this indication, it is 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 fail, the pressure increase between 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 receipt of an alarm. See also Relief Request SI-4 For the tank outlet valves, these valves are leak tested by pressurizing the downstream side of the valve and then determining the valve leakage by noting the change in SI Tank level.
Calvert Cliffs feels that these tests 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.
3.3 Thermal Raliaf Valvas Many safety related system, particularly those with heat exchangers, have been provided with relief valves. These relief valves are thermal relief valves (TRV) of small capacity intended to relieve pressure due to thermal expansion of fluid in a " bottled-up" condition. Experience has shown that failure of these valves will not result in failure of a system to fulfill its safety related function. Thus, thermal relief valves are not considered to perform a function important to safety and such valves have not been included in the program.
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% J ( J.4', Dald Bhutanen Tanttag Where the test frequency in Appandices C and D is specified as "C" (Cold Shutdown) the following definition for cold shutdown testing applies:
For unplanned or forced outages, testing will commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown (Mode 5) is achieved. Completion of all valve testing is not a prerequisite to subsequent startup. Any testing not completed at one cold shutdown will be performed during subsequent cold
' shutdowns (excluding refuelings) to meet as close as practical the specified Section II testing frequency. For planned outages where all required testing can be completed, exception to the above start time may be taken. >
Bowever, all testing must be completed consistent with Section II requirements prior to startup.
Appendix E specifically identifies those valves tested during Cold Shutdowns, with operational justifications for each. Yalves tested on a Cold Shutdown frequency may be tested in Modes 2, 3, 4, or 5 as appropriate for each specifAc valve (i.e., some valves may be tested during outage recovery, etc.).
35 Eart-stroka_Isating The goal of the Calvert Cliffs Inservice Test Program for valves is to perform full-stroke tests of all appropriate valves. With the exception of those valves for which specific relief has been requested, all valves will be full i stroke tested whenever possible.
Part-stroke testing of power-operated valves is generally not possible, due to valve logic circuitry which only allows full-open or full-closed valve movement. Moreover, the intent of Section KI is to assess valve operability through inservice testings while a part-stroke exercise does provide some measure of confidence in valve operability, it does not provide assurance of valve safety-related function. In addition, a part-stroke of a power-operated valve has the possibility, through human or mechanical error, to cause adverse plant consequences (isolation of cooling water, plant transients, etc.) via an j
inadvertent full-stroke. Based on the above, Calvert Clif fs will full-stroke l
test power-operated valves in accordance with the Valve Test Program (with 1 associated relief requests as appropriate).
Check valves whose safety function is to open will be full-stroked when possible. Since disk position is not always observable, the NRC staff has stated j that " verification of the plant 's safety analysis flow rate through the check I valve would be an adequate demonstration of full-stroke requirement. Any flow rate less than design will be considered part-stroke exercising 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 is passed through the valve. Check 4
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 exercise can not be confirmed, therefore, will be identified by an appropriate relief request. Calvert Cliffs feels that this position meets the intent of IWV-3522(b) regarding exercising of check valves.
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- -3.6 , Fall emfe Actumenen All those valves which have a fail-safe actuator are exercised normally using that actuator. Thus, the fail-safe actuator is regularly tested when the valve is tested.
3.7 Valva Positinn indicatnr Verification Verification of valve position indicator accurdcy will be performed in accordance with Section II Iwv-3300 with the exception of those valves for which specific relief has been requested. See also Relief Request A-2.
3.8 Eassiva valven l These 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 safety-function. Calvert Cliffs has categorized valves as passive which are administratively locked-open or locked-closed.in their safety-related position. Due to the lack o,f testing requirements. B-Passive valves have been excluded from Appendices C and D.
39 Strnko Times The valve stroke times identified in Appendices C and D may change due to modification, maintenance, etc. over plant lifetime. Calvert Cliffs will change these stroke times as necessary, incorporating the requirements of ASME Section XI, without further notification.
3.10 Shutdown cooling valves Power-operated valves used for Shutdown Cooling (SDC) function will be tested in accordance with ASME Section XI. Manual valves in the system that require a position change to align the systems for SDC 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 valves have been excluded from the associated Valve Test Program Tables.
3 11 Post-Maintenance Testing Valves tested on a Cold Shutdown frequency cannot be tested during power operation due to system limitations, personnel 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.
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- '3.12 huaf valwa Tameino Calvert Cliffs will perform all Relief Valve Testing identified in this program using POSRC-approved procedures under the requirements of the Technical Specification Surveillance Testing Program. This level of administrative control, including the requirements 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 qualifications and test group makeup, are met. In addition, the test personnel are trained and qualified in accordance with Calvert Cliffs Administrative Requirements for Surveillance Test Personnel. Therefore, the requirement of PTC 25.3 to have the test witnessed by a degreed engineer is not necessary. However, all test results of relief valve testing are reviewed by appropriate supervisory and engineering personnel prior to test acceptance.
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,' ..AEFERENCES I
i e 1983 Edition with Addenda through Summer 1983 ASME Boiler and Pressure Yessel Code - Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components l e Calvert Cliffs Nuclear Power Plant Units 1 & 21 Pipir.; and Instrument Diagram:
4 e Calvert Cliffs Nuclear Power Plant Units 1 & 23 Operations Drawings (see Appendix F) e Calvert Cliffs Nuclear Power Plant Units 1 & 2 Technical Specifications e CCI-104H Appendix 104.60 Attachment (4). Pages 1 through 28 - ASME Section XI Pump and Valve List e S'TP-M-571-1 (Revision 6) of LLRT-1. Pages 1 through 13 e STP-M-571-2 (Revision 13) of LLRT-1. Pages 218 through 230 e Unit 1 Pump and Valve Inservice Test Program.1st Ten Year Interval (see Apppendix C) e Unit 2 Pump and Valve Inservice Test Program. 1st Ten Year Interval (see Appendix C) e M-601 (Proposed Revision 26) Piping Class Summary Sheets - March 3. 1986 e 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 - August 30. 1982 (see Appendix H) e Safety Evaluation and Eadaral_Ragislar_Holica - December 22. 1982 (see Appendix B) e Safety Evaluation Granting Relief From ASME Code Section XI Inservice Testing Requirements - February 8. 1982 (see Appendix B) l Ref. 1-1 i
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- 1 REFERENCES e 1983 Edition with Addenda through Summer 1983 ASME Boiler and Pressure Vessel Code - Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components e Calvert Cliffs Nuclear Power Plant Units 1 & 21 Piping and Instrueent Diagrams e Calvert Cliffs Nuclear Power Plant Units 1 & 2 Operations Drawings (see Appendix F) e Calvert Cliffs Nuclear Power Plant Units 1 & 2: Technical Specifications e CCI-104H, Appendix 104.60 Attachment (4), Pages 1 through 28 - ASME Section XI Pump and Valve List e STP-M-571-1 (Revision 6) of LLRT-1, Pages 1 through 13 e STP-M-571-2 (Revision 13) of LLRT-1. Pages 218 through 230 e Unit 1 Pump and Valve Inservice Test Program, 1st Ten Year Interval (see Apppendix C) e Unit 2 Pump and Valve Inservice Test Program, 1st Ten Year Interval (see Appendix C) e M-601 (Proposed Revision 26) Piping Class Summary Sheets - March 3, 1986 e 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 - August 30, 1982 (see Appendix H) e Safety Evaluation and Endaral_Kagister_Hotica - December 22, 1982 (see Appendix H) e Safety Evaluation Granting Relief From ASME Code Section XI Inservice Testing Requirements - February 8, 1982 (see Appendix H)
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t APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 PUMP INSERVICE TESTING PROGRAM 9 O
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. APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 PUMP INSERVICE TESTINC PROGRAM l 1
Rii---rv nf Tnfnraatinn Prnvidad The pump test table provides the following information on testing requirements:
o Pump Name/No.
e ASME Class e Drawing on which the pump is depicted .
- e. Inlet Pressure ,
e Differential Pressure e Flow Rate e Vibration Amplitude e Observation of Lube Oil Level e Bearing Temperature e Speed Specific Relief Requests are identified as notes in the Tables, and immediately follow each Unit's Table. Test frequency for all parameters is identified by a "Q" for Quarterly, unless revised by Relief Request.
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- ' Unit 1 MLIEF EBQUEST MUBBER 1 System: Circulating Salt Water Cooling P&ID: OM-49 Pumps: Salt Water Pumps Nos.11,12, and 13 Class: 3 Impractical Test Requirement: IWP-3100 requirement to measure inlet pressure before 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 seven feet below Chesapeake Bay mean low water level; therefore, pump suction is a function of bay water level. Chesapeake Bay mean level is not considered to change during test performance.
Alternative Testing: Bay water level is recorded once during the test and used to compute pump suction pressure.
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. Unit 1 M N MQUEST MBBER 2 Systems Circulating Salt Water Cooling and Caponent Cooling Water MID: OH-49 and OM-51 Paps: Salt Water Pumps Nos 11,12, and 13 and Component Cooling Water Pumps Nos. 11, 12, and 13 Class: 3 Impractical Test Requirement: IWP-3100 requirement to observe proper lubricant level or pressure Basis for Relief: The salt water pumps and component cooling pumps have grease lubricated bearings. Therefore, observation of lubricant level or pressure is not appropriate.
Alternative Testing: None. The bearings are greased in accordance with the manufacturer's instructions on a regular preventative maintenance schedule.
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Unit 1 NELIEF EBQUEST MEBER 3 Systems: Chemical and Volume Control (both Charging and Boric Acid), Low Pressure Safety Injection, High Pressure Safety Injection, Containment Spray, Salt Water Cooling, Component Cooling, Auxiliary Feedwater, Service Water P&ID's: Various Pumps: All Safety Related Pumps Class: 2/3 Impract'ical Test Requirement: IWP-3100 requirement to measure bearing temperature.
Basis for Relief: The referenced code requires bearing temperature to be recorded annually. It has been demonstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure. Therfore, the detection of possible i bearing failure by a yearly temperature measurement is 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 pamp operating time required to obtain the measurements.
As an alternative, the pump vibration testing will be expanded from 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 requir' annual bearing temperature measurements per the ASME Section XI Code in order to assess pump mechanical condition.
Alternative Testing: Results of the regular vibration evaluation will be utilized to assess pump mechanical condition at least l quarterly. Results of this evaluation will be maintained ,
as a part of the Pump Record. !
I A-6
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" Unit 1 E LIEF W EIBGER 4 System: Chemical and Voltsee Control MID: OH-73 Pumps: Reactor Coolant Charging Pumps Nos.11,12 and 13.
Class: 2 Impractical Test Requirement: IWP-3100 requirement to measure pump suction pressure Basis foJr Relief: The reactor coolant charging pumps normally take their suction f rom the outlet of the volume control tank. The volume control tank is equipped with an automatic make-up system to prevent low level operation. If volume control tank level should decrease, a low level alarm is provided 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. Should the charging pumps be starved for flow as the result of a piping rupture or inadvertent valve 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 condition.
i A-7
l
'a , .
Unit 1 MLIEF MQUEST WINSER 5 Systems Chemical and Volume Control MID: OM-73 ,
Pumps: Reactor Coolant Charging Pumps Nos.11,12, and 13 Class: 2 Impractical Test Requirement: IWP-3100 requirement to measure pump differential pressure.
Basis for Relief: Due to pump design, the pump differential pressure is not indicative of pump performance. Positive displacement pump
- differential pressure varies across a wide spectrum, based on system conditions, without a change in flowrate.
Alternative Testing: Pump flowrate will be measured and used to assess pump hydraulic condition in lieu of pump differential pressure.
i A-8
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' Mnit 2 RELIEF E3 QUEST n e men 1 Systme Circulating Salt Water Cooling PSID: OM-450 Pumps: Salt Water Pumps Nos. 21, 22, and 23 Class: 3 Impractical hat nequirement: IWP-3100 requirement to measure inlet pressure before pur.p start and during test.
Basis 'for malief: 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 seven feet below Chesapeake Bay mean low water levels therefore, pump suction is a function of bay water level. Chesapeake Bay water level is not considered to change during the test.
Alternative hsting Bay water level is recorded once during the test and used to compute pump suction pressure.
A-11
i
. l 1
N, .
Unit 2 MLIEF BQUEST NUISER 2 System: Circulating Salt Water Cooling and Component Cooling water P61D: OH-450 and OM-452 Pumps: Salt Water Pumps Nos 21, 22, and 23 and Component Cooling Water Pumps Nos. 21, 22, and 23 Class: 3 Impractical Test Requirement: IWP-3100 requirement to observe proper lubricant level or pressure Basis for Relief: The salt water pumps and component cooling pumps have
'* grease lubricated bearings. Therefoi;e, observation of lubricant level or pressure is not appropriate.
Alternative Testing: None. The bearings are greased in accordance with the manufacturer's instructions on a regular preventative maintenance schedule.
A-12
t S. .
Unit 2 MLIEF MQUEST WINSER 3 Systems: Chemical and Volume Control (both Charging and Boric Acid), Low Pressure Safety Injection, High Pressure Safety Injection, Containment Spray, Salt Water Cooling, Component Cooling, Auxiliary Feedwater, Service Water P&ID's: Various Pumps: All Safety Related Pumps Class: 2/3 Impractical Test Requirement: IWP-3100 requirement to measure bearing temperature.
Basis for Relief: The referenced code requires bearing temperature to be recorded annually. It has been demonstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure. Therfore, the detection of possible bearing f ailure by a yearly temperature measurement is 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 l
expanded from one to multiple readings in two orthogonal directions.
These pumps are part of the Calvert Clif f s 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.
Alternative Testing: Results of the regular vibration analysis evaluation will be utilized to assess pump mechanical condition at least quarterly. Results of this evaluation will be maintained as a part of the Pump Record.
l A-13
- - - - - - _ _ _ _ - _ - _ _ _ - _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
e .,
N. .
- Snit 2 BELIEF MQUEST EWSER 4 Systems Chemical and volume Control P&ID: OM-461 Pumps: Reactor Coolant Charging Pumps Nos. 21, 22 and 23.
Class: 2 Impractical Test Requirement: INP-3100 requirement to measure pump suction pressure Basis ,for Relief: The reactor coolant charging pumps normally take their suction from the outlet of the voitune control tank. The volume control tank is equipped with an automatic make-up system to prevent low level operation. If voltane control tank level should decrease, a low level alarm is provided to alert the operator to the need for oorrective action.
If volume cor'*ol 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 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 condition.
l l
l I
A-14 l .
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l
\ .
. Unit 2 M LIEF MQUEST WINSER 5 Systems Chemical and Volume Control P&ID: OM-461 Pumps: Reactor Coolant Charging Pumps Nos. 21, 22, and 23 Class: 2 Impractical Test Requirement: IWP-3100 requirement to measure pump differential pressure.
Basis for Relief: Due to pump design, the pump differential pressure is not indicative of pump performance. Positive displacement pump
- differential pressure varies across a wide spectrum based on system condition, without a change in flowrate.
Alternative Testing: Pump flowrate will be measured and used to assess pump hydraulic condition in lieu of pump differential pressure.
1 l
' A-15
, 'N APPENDIX B EXPLANATION OF CODES AND SYMBOLS USED IN THE CALVERT CLIFFS VALVE INSERVICE TESTINC PROGRAM
-j This appendix defines the meaning of all codes and symbols used in the valve test program presented in Appendices C&D.
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5
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- - ... TABLE B-1 SYMBOLS USED TO DESIGNATE VALVE TYPE l
I VALVE TYPES f
sYMnOL MEANING C Check Valve B Butterfly Valve G Gate Valve GL Globe Valve RV Pressure Relief Valve RD Rupture Disk
- A Angle Valve 4
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- TABLE;B-2 SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE l YALVE ACTUATOR TYPES SYMBOL MEANIMC M Motor A Air S Sol'enoid H Hand (manual)
E/H Electro Hydraulic
- None (self actuating)
P/H Pneumatic Hydraulic B-3
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onv changes in valve function. ,
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j)'SYMBOLSUSEDTODESIGNATETESTINGREQUIREMENT c d ,4 b
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SYMBOL MRANINC i
- s. s F
Stroke Test per IWV-3400
- L Leak Test per 10CFR50 App. J.
Stroke test of check valves per V '
IWV-3520 t
S Set Point Test per IWV-3510
+1 e . I Isolation Test per IWV-3420 (see Section 3 2 of the program)
RR See Relief Request for testing i
s' The symbols shown on Tables B-4 and B-5 will be arranged in the following manner:
- A two-letter designation will show Test Method (first letter) and Test s
Frequency (second letter). Thus the designation "FQ" relates to a full-stroke test (with timing, as appropriate) per IWV-3400 performed quarterly. A designation of "VC" relates to a check valve exercise tes'c per IWV-3520 performed during Cold Shutdowns.
These symbols dill appear in the " Req. Test" column as well as the " Alt. Test" column, as appropriate.
t N
4 B-5 t
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- .> TABLE,B-5 SYMBOLS USED TO DESICNATE TEST FREQUENCY FREQUENCY 3I33Q1, MEANINC Q Quarterly R Refueling
.. T Per Table IWV-3510-1 C Cold Shttdowne (Plant in Modes 2.3.4.5.6)
- Frequency of Cold Shutdown is considered to be whenever the plant achieves a Mode 5 condition. Specific valves may be tested in Modes 2. 3. 4 or 5 as appropriate for each valve (i.e. valves may be tested while achieving or recovering from a Mode 5 condition).
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' . TABLE B-6 SYMBOLS USED TO DESIGNATE SECTION II VALVE CATECORY SECTION XI VALVE CATEGORY EYMBOL MEANINC A
Valves with specified maximum leakage rate.
(pressure system isolation valves (PSIVs) and containment isolation velves (CIVs)).
B Yalves with no specific maximum leakage rate.
C Self-actuating (check, relief valves)
D Actuated by energy source capable of only one operation (rupture disks.
explosive valves)
B-7
.. i
..' N. l 3 . i ITABLE B-7 f SYMBOLS USED TO DESIGNATE ACTIVE AND PASSINC VALVES ACTIVE & PASSIVE VALVES MEANINC SYMBOLS-1 Active - valves which are required to change position to accomplish a
- spe,cific function.
2 Passive --valves which are not required to change position to accomplish a specific function.
B-8
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.- 1 S. .
. 'APPENDII' C CALVERT CLIFFS UNIT 1 SECOND TEN YEAR VALVE TESTING PROGRAM SISIEM PLTD (OM 1 EAGE Main Steam 35 C-1 Condensate and Feedwater 39 C-2 Service Water 46 C-3 Salt Water 49 C-5 Component Cooling 51 C-7 Compressed Air 53 C-9 Fi*re Protection 56 . C-11 Fuel Pool 58 C-12 Ventilation System 65 C-13 Post-Accident Sample 66 C-15 Nitrogen Blanketing 68 C-17 Plant Heating 71 C-18 Reactor Ccolant 72 C-19 CVCS 73 C-20 Safety Injection 74 C-24 Waste Processing 76 C-30 RC Waste Processing 77 C-32 Waste Gas 78 C-34 Rad. Monitoring 98 C-35 Cas Analyzing 463 C-36 S.C. Blowdown 464 C-38 Plant Water & Air 479 C-39 Aux. Feedwater 800 C-41 1
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VALVE ASME P&lD VALVE SIZE VLV ACT POS. TIME NORM REQ. REQ. REQ. ALT.
NUMBER CLASS COORD CATIIX)RY (in.) TYPE TYPE IND. (sec.) POS. POS. TisT NO. TEST REMARKS 1-SV-103 1 J-7 B-1 3/4 G S X 3 C 0 FC A-1, A-2 RR 1-SV-104 1 J-6 B-1 3/4 G S X 3 C 0 FC A-1 A-2 PR 1-RV-2OO C-1 I 1 B-4 2 /2 RV - - -
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1 NELIEF EBQUEST NtNSER A-1 System: Various P&ID: Various valves: Various valves which have actual stroke times of 2 seconds or less Category: A and B active Class: Various Function's Various ,
Impractical Test Requirement: IWV-3413 to measure valve stroke time to the nearest second, and associated trending requirements of IWV-3417 Basis for Relief Valves with extremely short stroke 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-3413(b), a very small increase in stroke time will result in an extremely large percentage change, which could result in an unnecessary 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.
I 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 INV-3417(a) will, therefore, not apply, i
I c-43
a t-
- -> Unit 1 ELIEF MQUEST BENBER A-2 System: Various P&ID: Various valves: Various solenoid actuated valves Category: A and B Active Class Various Function: Various Impractical Test Requirement: IW-3300 requirement to locally verify remote position indication at least once every 2 years.
Basis for Relief: Rapid-acting solenoid actuated valves are self-contained units with no designed method of locally verifying position. By design, these valves are either full open or full closed, and valve design precludes the valves from remaining in an internal intermediate position.
Alternative Testing: Stroke testing of solenoid valves will serve to ensure valve operability. In addition, solenoid activated valves that do not have a method of locally verifying l
- position indication, which perform a containment isolation function, will be leak tested in accordance with the Appendix J Test Program at least every refueling.
1 l
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C-44
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IEELIEF MQUEST NUBBER VS-1 l
l l System: Ventilation System P&ID: OM-65, SH l valves: 1-CV-1410, 1-CV-1411, 1-CV-1412, 1-CV-1413 l'
Category: A-1 Class: 2 Functions Containment Isolation Impractical Test Requirennent: IW-3400 requirement to stroke test the valves quarterly.
Basis for Relief: These valves are normally locked shut with power removed. They are only required to stroke in Mode 6.
It is not desirable to stroke test these valves during each oold shutdown since unnecessary stroking could l cause degradation of the valve's leak-tight l capability. This would result in an unnecessary l increase in testing and valve maintenance.
l Alternative Testing: The valves will be full stroke tested on a refueling
- frequency.
l I
l C-45
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t- ,
- Units 1 & 2 EELIEF NBQUEST Nt3BER NG-1 Systes: Nitrogen Generating and Blanketing System P&ID: OM-68 Valves: 0-N2-3 4 4, 0-N2-3 4 5, 0-N2-3 4 6, 0-N2-3 47, 0-N2-3 48, 0-N2-3 49, 0-N2-389, 0-N2-392, 0-N2-395, 0-N2-398 Category: AC-2 Class: 2 Impractical Test Requirement: IW-3520 requirement to full-stroke exercise
- the valves quarterly ,
l 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.
Alternative Testing: These valves will be leak tested on a refueling schedule in accordance with the Calvert Cliffs Appendix J Program.
C-4~
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. Unit 1 EtLIEF W NUBSER RC-1 System: Reactor Coolant P&ID: OH-72 Valves: 1-ERV-402, 404 Category: C-1 Class: 1 Function: Relieve reactor coolant pressure.
Impractical Test Requirement: Setpoint test per IW-351,0.
Basis for Relief: These valves are categorized per Calvert Cliffs Technical 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 electric signal from a pressure measurement device.
Alternative Testing: Valves are tested 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 to serve as an MPT relief, and every 31 days there after when valve is required to be operable.
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.i Unit 1 NRLIEF MtQUllST 18tBSER SI-l System: Safety Injection and Contairunent Spray PGID: OM-74, SH 3 Valves: SI-316, SI-326, SI-330, SI-340 Category: AC-1 Class: 2 Functioni Containment Spray Header inlet checks, inside,and outside containment isolation valves.
Impractical Test Requirements: IW-3520 requirement to exercise the valves once every 3 months.
Basis for Relief: Check valves SI-316, SI-326, SI-330, and SI-340 cannot be stroked during operation without spraying large quantities of contaminated water into the containment. This contaminated refueling pool water is also borated to approximately 2300 ppm. Spraying the containment would result in a radioactive contamination cleanup problem and seriously damage components such as lagging, reactor coolant pumps, and control rod element assembly coils.
Alternative Testing: These 8-inch check valves will be disassembled at least once during the ITP interval to inspect the valves' internals.
1 l
C-48
t+ ,
OUnit 1 IELIEF ERQUEST NtNSER SI-2 Systems Safety Injection and Containment Spray P&ID: OM-74, SH 3 Valves: SI-4148, SI-4149 Category: C-1 Class: 2 Function: Containment Sump Outlet Check valves Impractical Test Requirement: IW-3520 requirement to exercise valves once every three months.
Basis for Relief: These check valves cannot be full-stroke exercised without 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.
Alternative Testing: The valves will be disassembled and inspected at least once during the ITP interval.
l C-49
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RELIEF REQUEST NUfBER SI-3 e t
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s *s System: Safety Injection ,
PEID: OM-74, SH 2
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Valves: 1-SI-215, 1-SI-225, 1-SI-235, 1-SI-245 ,4 Category: AC-1 ,
Class: 1 Function:* Safety Injection Tank discharge check valves, pressure system isolation valves Inpractical Test Requirement: -IWV-3520 requirement to full-stroke exercise valves.
Basis 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 floweste through these valves would require removal of the reactor vessel head and the flowrate required could cause damage to the core internals..
, Alternative Testing: The valves will be disassembled and, inspected once during the ITF interval. /,
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Unit 1 RELIEF REQUEST NUDEER SI-4 Syston: Safety Injection P&ID: OM-74, SH 2 Valves: 1-SI-217, 1-SI-227, 1-SI-237, 1-SI-247 Category: AC-1 Class: 1 Function: Safety Injection to RCS loop check valves, pressure system
., isolation valves Impractical Test Requirement: IWV-3100 requirement to test the valves' pressure isolation function.
Basis'for Relief: The pressure upstream of these valves is continuously monitored, and an increase results in an alarm in the
' control room, which requires operator action in ,
accordance with the Calvert Cliffs alarm manual. This 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 continuous monitoring provides assurance that these valves are meeting their pressure isolation safety function.
C-51
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s RELIEF REQUEST NUfEER SI-5 System Safety Injection s P&ID: OM-74, SH 2 ' ,,
Valves: 1-SI-217, 1-SI-227, 1-SI-237, 1-dI-247 Category: AC-1 Class: 1 ,
Function: Safety Injection to RCS loop check valves, pgessure system
. isolation valves Impractical Test Requirement: IW-3520 requirement to full-stroke exercise the valves.
Basis for Pelief: It is not possible to measure the flowrate through these valves nor to simulate rapid depressurization of the RCS. Additionally, achieving the design flowrate reactor vessel head and the flowrate required could cause damage to the core internals.
Alternative Testing: The valves will be disasstabled and inspected once duringlthe ITP interval. In addition, the valves are /
part-stroked wher.over shutdown cooling is in operation during cold shutdowns.
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- .APPENDIK D CALVERT CLIFFS UNIT 2 SECOND TEN TEAR VALVE TESTING PROCRAM EYSTEM PLTD (OM 1 R&gE Main Steam 36 D-1 Condensate and Feedwater 40 D-2 Service Water 46 D-3 Service Water 47 D-4 Fire Protection 56 D-5 Ventilation System 65 D-6 Yost-Accident Samp13 66 . D-8 Plant Heating 71 D-10 Waste Processing 76 D-ll R.C. Waste Processing 77 D-13 Waste cas 78 D-15 Rad. Monitoring 98 D-16 Salt Water Cooling 450 D-17 Component Cooling 452 D-19 Compressed Air 454 D-21 Reactor Coolant 460 D-22 CVCS 461 D-23 Safety Injection 462 D-27 Cas Anplyzing 463 D-33 S.C. Blowdown 465 D-35 Plant Water & Air 479 D-36 Aux. Feedwater 801 D-38
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i Unit 2 MIEF MQUEST NtNBER A-1 system: Various P&ID: Various Valves: Various valves which have actual stroke times of 2 seconds or less Category: A and B active class: Various Function: Various ,
Impractical Test Requirement: IWV-3413 to measure valve stroke time to the nearest second, and associated trending requirements of IWV-3417.
Basis for Relief Valves with extremely short stroke 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-3413(b), a very small increase in stroke time will result in an extremely large percentage change, which could result in an unnecessary 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.
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 INV-3417(a) will, 1 therefore, not apply.
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' Unit 2 EELIEF MQUEST WWSER A-2 System: Various P&ID: Various Valves: Various solenoid actuated valves Category: A and B Active Class Various Function: Various Impractical Test Requirement: IW-3300 requirement to locally verify remote position indication at least once every 2 years.
Basis for Relief Rapid-acting solenoid actuated valves are self-contained units with no designed method of locally verifying position. By design, these valves are either f ull open or full closed, and valve design precludes the valves from remaining in an internal intermediate position.
Alternative Testing: Stroke testing of solenoid valves will serve to ensure valve operability. In addition, solenoid activated valves that do not have a method of locally verifying position indication, which perform a containment isolation function, will be leak tested in accordance with the Appendix J Test Program at least every refueling.
D-41
Unit 2 RELIEF MQUEST NUMBER VS-1 System: Ventilation System P&ID: 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 Impractical Test Requirement: IW-3400 requirement to stroke test the valves quarterly.
Basis for Relief: These valves are normally locked shut with power removed. They are only required to stroke in Mode 6.
It is not desirable to stroke test these valves during each cold shutdown since unnecessary stroking could cause degradation of the valve's lead-tight capability. This would result in an unnecessary increase in testing and valve maintenance.
Alternative Testing: The valves will be full stroke tested on a refueling frequency.
D-42
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'I Unit 2 M LIEF IEQUEST NUBBER RC-1 Systems Reactor Coolant P&ID: OH-460 Valves: 2-ERV-402, 404 Category: C-1 Class: 1 Ftanction: Relieve reactor coolant pressure.
Impractical Test Requirement: Setpoint test per IW-3510.
Basis for Relief: These valves are categorized per Calvert Cliffs Technical 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 electric signal from a pressure measurement device.
Alternative Testing: Valves are tested 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 to serve as an MPT relief, and every 31 days there after when valve is required to be operable.
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Unit 2 NELIEF BEQUEST IIUBBER SI-l System: Safety Injection and containment Spray P&ID: OM-462, SH 3 Valves: SI-316, SI-326, SI-330, SI-3 40 Category: AC-1 Class: , ,2 Function: Containment Spray Header inlet checks, inside and outside containment isolation valves.
Impractical Test Requirement: IW-3520 requirement to exercise the valves once every 3 months.
Basis for Relief: Check valves SI-316, SI-326, SI-330 and SI-340 cannot be stroked during operation without spraying large quantities of contaminated water into the containment. This contaminated refueling pool water is also borated to approximately 2300 ppm. Spraying the containment would result in a radioactive contamination cleanup problem and seriously damage components such as lagging, reactor coolant pumps, and control rod element assembly coils.
Alternative Testing: These 8-inch check valves will be disassembled at least once during the ITP interval to inspect the valves internals.
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Unit 2 EELIEF MtQUEST IRBBER SI-2 System: Safety Injection and Containment Spray P&ID: OH-462, SH 3 Valves: SI-4148, SI-4149 Category: C-1 Class: 2 Ftmetion Containment Sump Outlet Check valves Impractical Test Requirement: IWC-3520 requirement to etercise the valves once every 3 months.
Basis for Relief: Check valves cannot be full-stroke exercised without 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 problein of the containment sump and associated equipment.
Alternative Testing: The valves will be disassembled and inspected at least once during the ITP interval.
D-45
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l Unit 2 MIEF EEQUEST EUBBER SI-3 1
System: Safety Injection PEID: OM-462, SH 2 Talves: 2-SI-215, 2-SI-225, 2-SI-235, 2-SI-245 Category: AC-1 Class:' 'l -
Function: Safety Injection Tank discharge check valves, pressure system isolation valves Inpractical Test Requirement: IW-3520 requirement to full-stroke exercise 2 valves.
Basis 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 cause damage to the core internals.
Alternative Testing: The valves will be disassembled and inspected once during the ITP interval.
D-46
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Unit 2 RELIEF REQUEST NU9BER SI-4 System: Safety Injection P&ID: OM-462, SH 2 valves: 2-SI-217, 2-SI-227, 2-SI-237, 2-SI-247 Category: AC-1 Class: 1 Function
- Safety Injection to RCS loop check valves, pressure system isolation valves Impractical Test Requirement: IWV-3400 requirement to test the valves' pressure isolation function.
Basis for Relief: The pressure upstream of these valves is continuously monitored, and an increase results in an alarm in the 4 control room, which requires operator action in accordance with the Calvert Cliffs alarm manual. This 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 continuous monitoring provides assurance that these valves are meeting their pressure isolation safety function.
D-47
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l Unit 2 RELIEF MEQUEST NUMBER SI-5 System Safety Injection .
P&ID: OM-462, SH 2 Valves: 2-SI-217, 2-SI-227, 2-SI-237, 2-SI-247 Category: AC-1 Class: 1 Function: Safety Injection to RCS loop check valves, pressure system
'* isolation valves .
Impractical Test Requirement: IWV-3520 requirement to full-stroke exercise the valves.
Basis 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 cause damage to the core internals.
Alternative Testing: The valves will be disassembled and inspected once during the ITP interval. In addition, the valves are part-stroked whenever shutdown cooling is in operation during cold shutdowns.
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D-48
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APPENDIX E VALVES TESTED DURINC COLD SHUTDOWN O
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- APPENDIX 2 YALVES TESTED DURING COLD SHUTDOWN Erstem Hg11 Valva Mn=bar Justiftrattan Valves cannot be full stroke Main steam & 1/2 2-CV-4043 Reheat 2-CV-4048 tested during plant operation 1-CV-4043 without causing major plant 1-CV-4048 transients / plant shutdown.
Condensate & 1/2 1-FW-133 Exercising these normally open 2-FW-133 valves would require a Feedwater 1-FW-130 cessation of feedwater flow to 2-FW-130 the steam generator. Therefore 1-MOV-4516 the valves are full stroke 2-MOV-4516 tested in Mode 5 at 3 month 1-MOV-4517 intervals as allowed by Section 2-MOV-4517 KI Article IWV-3410 Service Water 1/2 1-CV-1600 Exercising these valves during Cooling System 1-CV-1637 operation would stop cooling 1-CV-1638 water flow to the main turbine 1-CV-1639 auxiliaries and other vital 1-SRW-323 secondary plant equipment 1-SRW-324 necessary for power operation.
1-SRW-325 Valves are full stroke 2-CV-1600 exercised in Mode 5 at 3 month 2-CV-1637 intervals as allowed by Section 2-CV-1638 KI Article IWV-3410 2-CV-1639 2-SRW-323 2-SRW-324 2-SRW-325 Component Cooling 1/2 1-CV-3832 Exercising these valves during 1-CV-3833 operation would stop cooling water flow to the reactor 2-CV-3832 coolant pumps and other vital 2-CV-3833 equipment necessary for power operation. Valves are full
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stroke exercised in Mode 5 at 3 month intervals as allowed by Section XI Article IWV-3410 E-1
.s:
.]l311 , Walwa Musaher ,,Justifiemtinn
- tystmen Compressed Air 1/2 2-MOV-2080 Exercising these valves Plant & 2-IA-175 requires isolating instrument 1-IA-337 air to the containment thereby Instrument 1-MOV-2080 failing numerous air operated valves. Although control of these valves is not required during an accident it is )
required for normal reactor operation. Therefore, these <
valves are full stroke l exercised in mode 5 at 3 month i intervals as allowed by Section l 11 Article IWV-3520 l 1
Venti)4 tion System 1/2 1-HP-6900 Valves required by Tech. Spec.
1-HP-6901 to be maintained closed during l 2-HP-6900 Power Operation.
2-HP-6901 Reactor Coolant & 1/2 1-SV-6529 These valves are normally Waste Process 2-SV-6529 closed during power operation.
They do not get an automatic isolation signal. so opening these valves during power operation would decrease containment integrity.
Reactor Coolant 1/2 1-SV-103 Stroking valves during plant System 2-SV-103 operation could cause failure
- i 1-SV-104 to resent properly thus 2-SV-104 reducing plant reliability.
1-SV-105 Valves are full stroke 2-SV-105 exercised in Mode 5 at 3 month j 1-SV-106 intervals as allowed by I 2-SV-106 Section XI Article IWV-3410 E-2
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- t. : '.Agalas . . En11 - .Talve Mumher.- . . ..Inaeifiemtian CVCS 1/2 1-CYC-162 Valves cannot be stroked during 2-CVC-162 operation without stopping all 1-CVC-184 charging pumps. This would 2-CVC-184 place excessive cycles on 1-CVC-435 starting and stopping charging 2-CVC-435 and letdown. Therefore valves 4
are full stroke exercised in Mode 5 at 3 month intervals as allowed by Section XI Article IWV-3520 CVCS 1/2 1-CVC-235 Exercising these valves 2-CVC-235 requires injecting concentrated 1-CVC-228 boric acid directly into the 4
2-CVC-228 reactor coolant system. The
- resultips rapid power decrease would unnecessarily hazard plant reliability. Therefore, the valve is full stroke exercised in Mode 5 at 3 month intervals as allowed by Section XI Article IWV-3520 1/2 1-MOV-501 Valves cannot be stroked during CVCS 2-HOV-501 operation without stopping all 1-CV-515 charging pumps. This would.
1-CV-516 place excessive cycles on 2-CV-515 starting and stopping charging 2-CV-516 and letdown. Therefore valves are full stroke exercised in Mode 5 at 3 month intervals as allowed ~by Section XI Article ,
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IWV-3410 1
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CVCS 1/2 1-CV-517 Valves cannot be stroked 2-CV-517 during plant operation due to 1-CVC-185 (open) the resultant thermal stress to 2-CVC-185 (open) to the spray line and spray ,
nozzle. Valves will be full- l stroke exercised in Mode 5 at 3 month intervals as allowed by IWV-3410/3520 I
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< ralwa numhnr 1. h eifiemeean CYCS 1/2 1-CYC-186 Exercising these valves '
2-CVC-186 . requires personnel access to 2-CVC-187 high radiation areas within the 1-CVC-187 containment during plant 1-CVC-185 (shut) operation. Man rem exposure if 2-CYC-185 (shut) the valves were stroked during operation would be greater than 100 aren gamma and 50 arem neutron. Therefere, the valves are full stroke exereired'in Mode 5 at 3 month intervale as allowed by Section II Article IXV-3520 1/2 1-CVC-505 Valves cannot be stroked during CVCS , ,
2-CVC-505 plant operation without 1-CVC-506 stopping RCP seal bleed off 2-CVC-506 flow reducing RCP seal reliability. Valses are full stroke tested on Mode 5 at 3 month-Intervals as allowed by Section XI' Article IWV-3410 t-1/2 1-SI-113 Valves canno. be stroked during Safety Injection Containment Spray 2-SI-113 operation as this would require System 1-SI-123 depressurizing the reactor 2-51-123 coolant system. Therefore, the 1-SI-133 valve is full stroke exercised 2-SI-133 in Mode 5 at 3 month intervals ;
1-SI-143 as allowed by Section XI l 2-SI-143 Article IWV-3520 1-51-446 2-SI-446 1-SI-434 2-SI-434 1-SI-427 2-SI-427 ,
1-SI-414 2-SI-414 l 1-SI-405 i 2-SI-405 <
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Safety Injection 1/2 2-SI-118 See Previous Page Containment Spray 1-SI-114 System (CONT *D) 2-SI-114 1-SI-128 2-SI-128 1-SI-124
- 2-SI-124 1-SI-138 2-SI-138 1-SI-134 2-SI-134 1-CV-306 2-CV-306 1-SI-148 2-SI-148 1-SI-144
- .. 2-SI-144 ,
1-SI-313 2-SI-313 1-SI-323 2-SI-323 1-MOV-651 2-MOV-651 1-MOV-652 2-MOV-652 1-SI-4146 2-SI-4146 1-SI-4147 2-SI-4147 Cas Analyzing 1/2 2-SV-6531 These valves are normally System 1-SV-6531 closed during power j 2-SV-6540 A thru C operation and are not i 1-SV-6540 A thru C required to open. Opening 2-SV-6507 A thru C these valves during power 1-SV-6507 A thru C operation would decrease containment integrity.
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Auxiliary Feed- 1/2 2-AFW-129 Exercising these valves during water System 1-AFW-129 plant operation would require l J
2-AFW-130 feeding hot steam generator 1-AFW-130 with cold feedwater thereby 2-AFW-102 thermally shocking the 1-AFW-102 auxiliary feedwater ring within 2-AFW-116 the steam generator. Therefore 1-AFW-116 the valves are full stroke 1-AFW-193 exercised in Mode 5 at 3 month 2-AFW-193 intervals as allowed by Section 1-ATW-199 XI Article IWV-3520 2-AFW-199 1-AFW-194 2-AFW-194 1-ATW-200 2-AFW-200
,, 1-ATW-183 2-AFW-183 1-AFW-190 2-AFW-190 E-6
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.. g APPENDIX F DRAWINGS USED IN PREPARATION
,3
. APPENDIX F DRAWINGS USED IN PREPARATION Drawing Revision / ehmat No.
Bata Title Unit bla .
1 1 OM-35 18/2-20-85 Main Steam & Reheat 1 2 OH-36 20/6-5-85 Main Steam & Reheat 4 1 OH-39 5/7-1-86 Condensate & Feedwater 4 2 OH-40 5/8-20-86 Condensate & Feedwater Service Water Cooling 1 1 OH-46 12/8-8-86 Service Water Cooling 2 1 OH-46 . 14/8-8-86 .
Service Water Cooling 1 2 OH-47 10/3-13-86 Service Water Cooling 2 2 OH-47 12/8-8-86 Circulating Salt Water Cooling 1 1 OH-49 17/7-1-86 Circulating Salt Water Cooling 2 1 OH-49 9/12-17-86 1 1 OH-51 16/7-30-86 Component Cooling System 2 1 OH-51 5/7-2-86 Component Cooling System 3 1 OH-51 8/6-16-86 Component Cooling System 1
OH-52 7/10-16-84 Containment Charcoal Filter 1 Spray 1
OH-53 14/8-19-86 Compressed Air: Instrument 1 and Plant 1
OH-53 3/3-7-85 Compressed Air: Instrument 2 and Plant 1
OH-53 10/8-19-86 Compressed Air: Instrument 3 and Plant 1
OH-53 1/3-26-85 Compressed Air: Instrument 4 and Plant 1&2 OH-56 5/11-15-85 Plant Fire Protection 2 1&2 OH-58 16/10-28-86 Spent Fuel Pool Cooling & 1 Pool Fill and Drain F-1
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Drawing Revision / l
. me. e mate Iltla ,iBhmet Ho. . . . Iln11 OH-59 19/11-6-86 Well Water. Pretreated Water. I 1&2 Domineralized Water, and Condensate Storage OH-65 12/1-4-85 Ventilation 1 1&2 OH-65 12/12-11-85 Ventilation 2 1&2 OH-65 5/10-4-84 Ventilation 3 1&2 OH-65 7/9-3-86 Ventilation 4 1&2 OH-66 20/7-7-86 Reactor Coolant and Waste 1 1&2 Process Sample OH-66 6/2-21-86 Reactor Coolant and Waste 3 1&2
.* Process Sample ,
OH-68 10/1-21-86 Nitrogen Generating & Blanketing 1 1&2 OM-71 4/10-23-84 Plant Beating 2 1&2 OM-72 23/4-11-86 Reactor Coolant 1 1 OM-72 OA/7-31-86 Reactor Coolant 2 1 OH-73 31/11-21-86 Chemical & Volume Control 1 1 OH-73 13/8-25-86 Chemical & Volume Control 2 1 OH-73 13/4-14-86 Chemical & Volume Control 3 1 OH-74 26/5-9-86 Safety Injection & Containment 1 1 Spray OH-74 7/5-20-85 Safety Injection & Containment 2 1 Spray ,
OH-74 4/5-1-85 Safety Injection & Containment 3 1 Spray OH-76 9/6-19-85 Waste Process Equipment & 1 1 Area Drains OH-76 12/4-17-86 Waste Process Equipment & 2 1 Area Drains OM-76 13/5-20-86 Waste Process Equipment & 3 1 Area Drains OM-76 1/4-21-86 Waste Process Equipment & 4 1 1 Area Drains l F-2 l
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.- . Drawing .. Revision /
- h. Bate < ' ' Title * ,
- Ehant No. . Ilnit 13/5-12-86 Reactor Coolant Waste Processing 1 162 OM-77 Reactor Coolant Waste Processing 3 1&2 OH-77 8/5-12-86 Waste cas & Misc. Waste 1 1&2 OM-78 20/8-8-86 Processing 8/8-8-86 Weste cas & Misc. Weste 2 1&2 r OH-78 Processing Area & Process Radiation 1 1&2 OM-98 16/7-7-86 nonitoring Chemical Addition & Condenser 1 1&2 OH-115 10/4-28-86 Tube Bulleting 4/1-6-86 Chemical Addition & Condenser 2 1&2 OH-115' Tube Bulleting 3/7-7-86 Chemical Addition & Condenser 3 1&2 OH-115 Tube Bulleting 13/10-31-86 Circulating Water Cooling 1 2 OM-450 16/12-20-85 Circulating Water Cooling 2 2 OH-450 16/1-23-86 Component Cooling 1 2 OH-452 OH-452 1/10-8-84 Component Cooling 2 2 OH-452 8/6-16-86 Component Cooling 3 2 OH-453 7/4-28-86 Containment Charcoal Filter 1 2 Water Spray OH-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 OH-454 2/3-5-86 Compressed Air: Instrument 4 2 and Plant OM-460 18/1-30-86 Reactor Coolant 1 2 OH-460 OA/10-9-86 Reactor Coolant 2 2 F-3
'4 -
. A, "Y ,.
. Drawing iRevision/ )
me. nat. Title th==t un. Un11 !
Chemical & Yolume Control 1 2 OM-461 25/7-2-86 2
OM-461 3/12-17-84 Chemical & Volume control 2 i
3 2 OM-461 8/5-12-86 Chemical & Yolume Control m
Safety Injection & Containment 1 2 f OH-462 26/8-13-86 Spray Safety Injection & Containment 2 2 OH-462 6/3-11-86 Spray Safety Injection & Containment 3 2 OH-462 3/12-10-84 Spray 8/3-10-86 Cas Analyzing 1 1&2 OH-46,3, Cas Analyzing 2 1&2 OH-463 5/8-5-86 Steam Generator Blowdown 1 OH-464 12/7-7-86 1 Recovery 12/4-21-86 Steam Generator Blowdown 1 2 OM-465 Recovery OM-479 15/10-9-86 Plant Water & Air Service 1 1&2 OH-479 7/3-28-66 Plant Water & Air Service 2 1&2 OH-800 10/10-16-86 Auxiliary Feedwater 1 1 OH-801 10/9-29-86 Auxiliary Feedwater 1 2 l
F-4 1
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