ML20237E219
| ML20237E219 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/17/1987 |
| From: | Leblond P COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 3932K, TAC-61855, TAC-61856, NUDOCS 8712280218 | |
| Download: ML20237E219 (145) | |
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e tt 's y CommonwC:lth Edisen One First National Plaza, Chicago, Illinois OE, V Address Reply to: Post OIEe Box 767 Chicago, Illinois 60690 0767 December 17, 1987 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 l
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Subject:
Zion Nuclear Power Station Units 1 and 2 l Second Interval Inservice Testing Program j NRC Docket Nos. 50-295 and 50-304 j
. TAC Nos. 61855/56 l
Reference:
March 31, 1987 letter from J.A. Norris to D.L. Farrar 1
Gentlemen:
This transmittal is providing the NRC Staff with Revision 4 to Zion Station's Second Interval Inservice Testing (IST) program.
The referenced letter requested additional information regarding Zion Station's Second Interval IST program. In addition, the NRC Staff suggested that a meeting be held between NRC-NRR and Commonwealth Edison Company personnel. That meeting was held at Zion Station on July 28 and 29, 1987.
That meeting identified a number of items that required either clarification or alteration. It is these issues that have generated the need for Revision 4.
Attachment 1 to this letter specifically responds to the questions contained in the referenced letter. Attachment 2 provides a summary of the IST program changes reflected in Revision 4. Attachment 3 contains the altered pages comprising Revision 4 to Zion's Second Interval IST program.
Finally, Attachment 4 provides a brief history of the correspondence relating to the review of Zion's Second Interval IST program.
These revisions will necessitate the acquisition of additional instrumentation, alteration of existing procedures, and the generation of new procedures to reflect new test requirements. These activities are expected to be complete and the program revisions fully implemented by August 31, 1988.
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a US NRC December 17, 1987 If any further questions arise regarding this matter, please direct them to this office.
Very truly yours, P. C. LeBlond Nuclear Licensing Administrator Attachments cc: Resident Inspector - Zion J. A. Norris - NRR 3932K l
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- Attachment #1
- 1. Valve Testing Program A. . General Ouestions and Comments NRC Question #1: Valve Position #12 appears to request relief f rom a Code requirement. Therefore, suitable justification ,
must be provided demonstrating the impracticality of '
meeting the Code requirement. i CEC 0's Response: Valve position #12 will be deleted from the IST Program and safety / relief valves will be tested to the requirements of paragraph IWV-3513.
NRC Question #2: The Code (IWV-3416) states that valves in systems out ,
of service need not be exercised quarterly, however, these valves will be exercised within 30 days prior to return of the system to service. Are the valves addressed in Valve Position #13 in systems out of service?
CECO's Response: If a PORV is leaking by, the block valve shall be shut until the leakage is corrected. The PORV is considered out of service when the block valve is shut. The block valve shall be stroked prior to returning it to service. If a test frequency is missed, then the block valve shall be stroked at the next cold shutdown.
Containment Isolation valves that are out of service for isolation purposes shall be exercised prior to returning the valve to service. No change to Position
- 13 is required.
NRC Question #3: What criteria is utilized for assigning limiting values of full-stroke time for power operated valves?
CECO's Response: The criteria for assigning limiting stroke times is based on the FSAR or Technical Specifications. Where limiting values for stroke times are specified, the maximum stroke time for the valve will be equal to or less than that specified. The FSAR also gives guidelines to assign maximum stroke times for motor operated valves based on whether they are fast or slow acting valves. For other valves outside of the FSAR or Technical Specifications, limiting values were based on baseline data, manuf acturer's recommendation or engineering evaluation. All changes in maximum stroke times must go through on-site review for approval.
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- a NRC Question #4: The statement on page 212a '...where the Code requirement (sic) conflict with Zion's stated
" Positions", the Positions shall supersede Section XI' is unacceptable to the staff. The requirements of Section XI must be met unless specific relief is requested and subsequently granted.by the NRC.
CECO's Response: Zion Station will revise the statement on page 212a to read:
"Where a strict reading of the ASME requirements yields insufficient guidance to implement-the Code at Zion Station, the Zion's stated Positions will be utilized as clarification and will define the Station's interpretation of the Code."
The purpose of a Position is not intended to exclude Code requirements but rather to define the Station's interpretation of the requirement. ,
B. Condensate Strirage System NRC Question #1: Do valves MOV-FWOO74, 0075, and 0076 perform a safety function in the closed position?
CEC 0's Response: The FSAR does take credit for the Service Water system being a backup supply for the Auxiliary Feedwater pumps. Using service water would be a 'last resort' solution after other attempts to restore the normal supply system. These valves will be stroke timed closed at cold shutdown due to their- need to be closed should the unlikely event requiring service water as a supply arises.
C. Diesel Oil / Generator System NRC Question #1: Provide P&ID's No. M-38 and M-530.
CECO's Response: P&ID's were provided July 28, 1987.
NRC Question #2: Can one diesel air start check valve be verified to full-stroke open during each regularly scheduled diesel generator test (monthly?) to satisfy the Section XI quarterly test requirement for each valve.
CECO's Response: No, one diesel air start check valve cannot be verified Jto full stroke open during each regularly scheduled diesel generator test. In order to test one of the check valves individually one receiver would have to be isolated thereby eliminating redundancy and possibly placing the plant in a less conservative mode of operation. At least one air start check valve is .
partially stroked each time the diesel generator is started. This test requirement will be verified qua rte r ly. Valve relief #16 will be revised.
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NRC. Question #3: Valve Relief #30 is not necessary since valve full-stroke is defined by the NRC as opening sufficiently to pass the maximum flow rate identified in any of the plant's safety analyses.
CECO's Response: Valve Relief #30 shall be withdrawn.
D. Isolation Valve Seal Water System NRC Question #1: The information presented in Valve Position #10 is a deviation from the Code requirements, therefore..a specific request for relief must be provided with a g detailed technical justification demonstrating the j impracticality of complying with the Code requirements. ;
Ceco's Response: Valve Position #10 has been withdrawn and replaced with Valve Relief #32. This requests relief f rom trending the stroke times of LCV-1WO1, 2 and PCV-IWO3. Since the only test method to stroke the valves cannot provide repeatable values. A maximum stroke time will be assigned to the valves.
E. Containment Spray System NRC Question #1: Valve Relief #13 is unnecessary since the longest interval between tests is at least as often asSection XI requires.
Ceco's Response: Valve Relief #13 is not requesting relief from the test frequency but is instead requesting relief to perform Leak Testing in accordance with 10 CFR 50, Appendix J leak testing. Valve Relief #13 shall be revised to more clearly state this and all valves which are leak tested in accordance with 10 CFR 50, Appendix J will also be added. Valve Relief s #2, #14 and #28 will also be revised or withdrawn.
NRC Question #2: Why were valves MOV-C50002, 0004, and 0006 categorized A and not leak-tested and valves MOV-C50005, 0009, and 0013 not categorized A when they are leak tested?
CECO's Response: Valves CS0005, 9 and 13 are not m Jer operated valves. Based on the new Containment Isolation Valve Technical Specification, valves MOV-C50002, 4, and 6 shall be Category B and will not be leak tested.
Valves C50005, 9 and 13 are Category A/C containment isolation valves and will be leak tested.
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4 F. Chemical and Volume Control System NRC Question #1: Has the ultrasonic flow instrumentation been pernenently installed in the charging pump mini-flow line (see Valve Relief #23) to verify the full-stroke capability of valves VC8542A and B quarterly?
CECO's Response: No, the instrumentation has not been installed. An alternative means has been utilized to measure the flow through the mini-f low line. Valve relief #23 has been revised.
G. Residual Heat Removal System NRC Question #1: Valve Relief #4 is unnecessary since valves RH8730A and B are being exercised during cold shutdowns in accordance with the Code requirements.
CECO's Response: Valve Relief #4 has been withdrawn and Position #17 has been added to explain why the valves are partial stroked quarterly and full stroke exercised at cold shutdown.
NRC Question #2: How is full flow verified through each of valves RH8736A and B and RH8749A and B?
CECO's Response: Presently our test method does not measure flow through each of the injection legs individually. The procedure will be revised prior to the 1988 U-1 refueling outage to individually instrument each of the RHR hot leg injection lines in order to measure the flow through each leg. Additionally the Station is still investigating a analytical method to verify flow through each leg based on the flow limiting orifices already installed in the RHR system. Valve Relief 15 has been revised.
NRC Question #3: Can valve RH8958 be full-stroke exercised quarterly utilizing the test line to the refueling water storage tank via S18735?
CECO's Response: No, valve S18958 cannot be full stroke exercised quarterly utilizing the test line .to the RWST via S18735. During power operation the RHR system must be operable and the system lined-up for safeguards actuation. By opening S18735, the RHR injection flow would be significantly reduced thereby not providing design analysis flow to the reactor core in the event of a double ended severence of a cold leg loop.
Current system configuration has no alternative suction source for the RHR pumps.
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- j H. Safety Injection System NRC Question #1: How is full-stroke verified for each of the following valves:
H Valve 1
i SI8905 A and B S19849 A and B '
S19004 A and B SI9012 A thru D CECO's Response: Valves S18905 A. B and SI9004 C. D !
Presently the Station does not measure the flowrate through each line. The test procedure shall be revised to measure the flow through each line using temporarily installed differential pressure gauges.
Valves SI8949 C and D These valves are 8" swing check valves and would require at least a 700 GPM flow rate in each line to obtain full disk lif t. Design flow of the safety injection hot legs is not sufficient to obtain full disk lift. Therefore, these valves will be partial stroked each refueling outage, this is acceptable practice per the NRC's definition of full stroke.
Flow will be verified by individually instrumenting '
each line with dif ferential pressure gauges.
Valves SI9012 A. B. C and D Currently flow rates are measured in each line using temporarily installed dif ferential pressure gauges.
NRC Question #2: Has a test been implemented to verify closure of valve S189127 CECO's Response: Closure of valve S18912 is verified by measuring seat leakage. Leakage measured by utilizing charging pump discharge to pressurize up to the check valve. Any leakage past the check valve is recorded on a pressure gage upstream of the check valve. This verifies proper closure and condition of the valve seat. This test shall be performed every refueling outage. Valve Relief #21 has been revised.
NRC Question #3: Have the accumulator discharge check valves, S18948 A thru D and S18956 A thru D, been full-stroke exercised (see Valve Relief #9) by dumping the accumulators under nitrogen pressure into the partially drained refueling cavity during refueling with the reator vessel head removed? How is the flow-rate through these valves measured?
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CECO's Response: The Station provided'the NRC with a copy of the test procedure and the results of testing. The flowrate is calculated by the level change in the accumulator over a period of time. Results have shown that full disk lift is obtained. Additional information has been added to Valve Relief #9.
NRC Question #4: Is the flow through valves SI9001A thru D and SI9002A through D suf ficient to verify their f ull-stroke capability during cold shutdown residual heat removal operations? 7 i
CECO's Response: In the cold leg section of the RHR check valve verification test, TSS 15.6.85, full disc lif t of the ,
check valves is verified by an indirect method. The '
system is arranged such that each of two RHR cold leg headers feeds two injection legs. Both headers have flow instrumentation installed (FI-970 and F1-971).
All four injection legs have two check valves in series (51-9001 and SI-9002) and a flow limiting orifice which partitions flow through each leg to approximate!y 25 percent.
In 155 15.6.85 RHR discharge is directed through the parallel cold leg headers and flow is measured on FI-970 and FI-971. A ratio of F1-970 to F1-971, in theory, should equal 1.0 if there are no flow restrictions through any header or leg. If flow is restricted in an injection leg due to a partially l closed check valve. This will be indicated on the header flowmeter. Flow through the unrestricted legs will increase but remain equal relative to each other. For example under normal conditions total pump flow is approximately 3600 GPM and measured flow on F1-970 and FI-971 is 1800 GPM each. Flow through each injection leg can reasonably be estimated at 900 GPM due to the flow balancing effects of the installed orifices. Because full disc lift of the check valves occurs at 690 GPM these check valves are v?rified to be operable. In another example, if FI-970 and F1-971 indicate 2000 and 1600 GPM respectively, one can assume flow past F1-970 is evenly divided through the two legs at 1000 GPM each. This implies that flow through one leg downstream of FI-971 is also 1000 GPM and flow through the remaining leg is 600 GPM. 600 GPM through this leg indicates the check valves are not achieving full disc lift.
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Acceptance criteria has been generated to assure that approximately 760 GPM goes through each injection leg. This is based on a calculated requirement of 690 GPM for full disc lif t and a safety and instrument l , uncertainty factor of 10.11%. At relatively low total pump flow rates of approximately 3200 GPM, the ratio l .of F1-970 to FI-971 must be very close to 1.0 to verify good flow partitioning and consequently that 760 GPM.is achieved through each leg. At higher pump flow rates, this flow ratio is allowed some variance f rom the theoretical 1.0. A higher variance implies that flow is not perfectly partitioned between the four legs; however as long as flow through each leg is calculated to be greater than 760 GPM, full disc lift has been verified. For example, if total pump flow is 4500 GPM and flow through FI-970 and FI-971 is 2007 and 2493 GPM respectively the ratio if 0.80. This suggests flow through one leg is 760 GPM and the other three legs is 1247 GPM each. Full disc lift has been achieved and therefore test results are acceptable.
Regarding increased test frequency, the procedure will be revised to verify full disc lift of the RHR cold leg injection check valves during each cold shutdown. Valve relief #27 will be revised and Position #18 added to explain why the valves are tested at cold shutdown vs. quarterly.
NRC Question #5: Has the ' leak-rate testing proposed in Valve Relief #25 been successfully performed or are valves 519002A thru D verified leak-tight by performing valve disassembly and inspection?
CECO's Response: Leak testing of SI9002A thru 0 has been successfully performed. Valve Relief #25 will be withdrawn.
NRC Question #6: Should valve SI8857 be categorized A/C since it appears to be leak-rate tested per Appendix J?
Ceco's Response: Valve 518857 will be categorized A/C, the valve is 10 CFR 50 Appendix J, lype C, leak tested.
I. Containment Air Monitoring System NRC Question #1: Valve Relief #14 is. unnecessary since the longest interval between tests on valves PR0029 and 0030 is at least as often asSection XI requires.
CECO's Response: Valve Relief #14 has been withdrawn and Valve Relief
- 13 has been revised to include all valves which are Type C leak tested in accordance with 10 CFR 50 Appendix J.
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- NRC Question #2: Should valve PR0029 be categorized A/C?
CECO's Response: Valve PR0029 will the categorized as A/C in the IST.
program.
NRC Question #3: Why is valve PR0030 leak-rate tested according to Appendix J but not required to be shut following an accident (see CECO's revised response to NRC Question P-3, Attachment 4, page 2, of the letter from P.C.
LeBlond to Harold R. Denton dated June 17,1986).
CECO's Response: Valve PR0030 is not required to be shut following an accident since valve PR0029 acts as the primary isolation from containment. Both PR0029 and PR0030 are installed in a Class 3 piping penetration as defined in section 6.6.2.1.3.B of the station's FSAR and are required for post-accident sampling. PR0029 fulfills the minimum requirement for isolating the containment atmosphere from a normally closed system outside containment, which exempts PR0030 from automatic isolation requirements. But PR0030 represents a redundant means of manually isolating containment.
J. Instrument Air System NRC Question #1: Provide a more detailed technical justification for not fuli-stroke exercising valves FCV-IA01A and IA01B during cold shutdowns.
Ceco's Response: Valves 3CV-IA01 A and B can be tested during cold shutdo.9. Valve Relief #22 shall be withdrawn and Position 19 shall be added to define why the valves are tested at cold shutdown vs. quarterly.
- 2. Pump Testing Program NRC Question #1: The statement on page 174a "...where the Code requirements conflict with Zion's stated " Positions",
the positions shall supersede section XI." is unacceptable to the staff. The requirements of Section XI must be met unless specific relief is requested and subsequently granted by the NRC.
Ceco's Response: The intent of a Position is to clarify vague statements in the Code. The Station uses the Position to define ~its interpretation of the Code's intent.
This statement in the program shall be revised.
NRC Question #2: Provide a more specific technical justification for not meeting the allowable ranges of test quantities as specified in TABLE IWP-3100-2 (see Pump Position #1).
Ceco's Response: Per IW'-3210, the Owner may adjust the allowable ranges of Table IWP-3100-2. Pump Position #1 has been expanded to include additional information on the +10%
range.
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9 NRC Question #3: Since the component cooling water pumps, OCC003 thru 000007, are known to be operating slightly above the manufacturer's provided pump curve, pump specific curves or repeatable reference values should be developed for each of.these pumps and the alert and required action limits.as specified by the Code should '
be applied to these unique curves (see Pump Relief #1). <
CECO's Response: Pump Relief #1 will be deleted. Information on the expanded alert and required action ranges has been included in Pump Position #6.
NRC Question #4: The NRC rec nizes that operation of only one service water during power operation at Zion Station is.
impractical for performance of the Section XI required testing. However, a test method should be developed that provides information similar to that required by the Code for quarterly evaluation of operational readiness and pump degradation for the service water pumps, SW001, 002, and 003 (see Pump Relief #2).
CECO's Response: The service water pumps are tested monthly to ensure adequate cooling is being provided throughout the plant. In the testing, the pumps are operated for at-least four hours, vibration and discharge pressures are recorded and the lubrication level is checked.
Currently there is insufficient straight length pipe to install any type of flow instrumentation that could accurately measure flow. The discharge piping is two feet in diameter and normally at least 10 times the diameter of straight length pipe is necessary for installation of flow instrumentation. The discharge piping before entering the common header is only 10 f t in length and is curved. Therefore there is insufficient straight. length pump discharge piping except in the common header.
NRC Question #5: The NRC 5taf f agrees that measurement of vibration velocity for safety related pumps can provide better information for evaluation of pump degradation and assessment of continued operability than measurement of vibration displacement as required by Section XI.
However, the only NRC Staf f acceptable criteria is provided in ASME OM-6, Draf t 8. " An American Nationa l Standard In-Service Testing of Pumps" (see Pump Relief
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' i CECO's Response: Supplemental Information on Zion's Vibration Program l Zion Station's vibration program dif fers f rom the OM-6 document in two areas; measurement and action range levels. (Alert ranges of the OM-6 document are not ]
applicable since we already test at an increased f requency except for the diesel oil transfer pumps).
Zion Station measures vibration in RMS in place of peak to peak. Measuring in RMS.is the best indicator of vibration severity because it more truly represents the area under the f requency curve. Peak to peak measurements represent only an infinitesimal moment in time and are not always repectable values.
The success of Zion's vibration program is due to the trending program. Therefore it is imperative to have repeatable and reliable data for trending from month to month. RMS values have proven to be excellent indicators of pump degradation and small vibration increases have been easy to spot. Zion Station previously measured vibration readings using peak to I peak valves, which were not always representative of the true vibration characteristics, was unreliable for trending because there were random fluctuations from month to month.
Zion Station also conf licts f rom the OM-6 document in setting the action range level for pump vibration. If the units in Table 6100-1 were RMS instead of peak to peak, Zion would be at least as conservative in two cases and more conservative in most cases as the OH-6 document.
Converting the maximum allowable peak to peak ranges to RMS, approximately 62% of our pumps have equal or n' ore restrictive requirements and 37% would have less restrictive requirements. In no case is the allowable limit greater than .709 in/sec (RMS). Comparing the Canadian Standard 53% of Zion's pumps have more conservative limits, 47% are as restrictive. In no case are less restrictive limits used.
in addition to the required action range, Zion Station trends all vibration data and has also specified its own alert ranges which in all cases is more conservative than the required action range of Table l
6100-1 (converted to RMS). If equipment reaches this alert level, the pump will be evaluated as to whether l continued operation will appreciably degrade the pump )
l- in which case it will be taken 005. Otherwise the pump will be scheduled for maintenance at the next I outage. During an outage, any pump operating in the alert range will be overhauled prior to startup. (The l containment spray diesel pump is an exception, it has been operating in the alert range for 12 years with no degradation.) Maintenance is often scheduled on equipment that hasn't reached the alert level when the vibration analyst spots an adverse trend upward.
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If'it even becomes apparent that a pump is not-protected adequately,-Zion is required to reduce the limits.
Because of Zion's rigorous trending program and our.
commitment to fixing a pump when any slight adverse trends are spotted, we feel that our program, as it stands, is an excellent and sensitive detector of pump degradation and will adequately monitor pump performance to help ensure that all vibration problems are fixed prior to having to declare a pump inoperable.
NRC Question #6: What alternative testing is proposed in Pump Relief #4 in lieu of the Code ' required pump bearing temperature measurements?
Ceco's Response: Vibration velocity is used to monitor pump bearing cond' tion in lieu of bearing temperature measurements. Pump Relief #4 has been revised to explicitly state this.
NRC Question #7: From which Code requirements is relief being requested in Pump Relief #67 Does the installed instrumentation meet the accuracy requirements of Section XI, Table IWP-4110-1?
CECO's Response: The installed instrumentation does meet the requirements in Table IWP-4110-1. Pump Relief #6 has been rewritten to not only clarify this point but also to request relief f rom measuring suction pressure and differential pressure since these are positive displacement pumps and flow and pressure are independent variables. Per the meeting held on July 29, 1987, the NRC stated that only flow and discharge pressure need to be measured and compared to a minimum valve.
NRC Question #8: Has the instrumentation referenced in Pump Reliefs #7 and #8 been installed in these systems? Do these instruments meet the accuracy requirements of Section XI?
CECO's Response: The instrumentation referenced in Pump Reliefs #7 and 8 has been installed and meets the accuracy requirements of Section XI. Pump Reliefs #7 and 8 will be withdrawn.
NRC Question #9: How do the pump reference values established per IWP-3100 compare to the manufacturer's supplied pump curves? Is the full pump flow seen in the flow instrument indication or is a portion of the pump's flow diverted through the miniflow line?
Ceco's Response: Normally the pumps operate within +3/-4% of the manufacturer's pump curve.
No pump test is performed where the flowrate through the mini-flow line is added to the measured flowrate to adjust the observed flow to the pump curve.
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b NRC-Question #10: Why.has the test requirement for bearing temperature measurement and lubrication level or pressure considered N/A for the residual heat removal pumps-kH001 and 2 when the previous IST program specifically stated that these parameters would be measured and/or observed?
'CEto's Response: The previous submittal of the IST program erroneously indicated that bearing temperature measurements and lubrication level checks would be performed. The ,
residual heat removal pumps have no bearings or :
bearing lubricant, therefore these measurements cannot i be performed.
NRC Question #11: Why were the spent fuel cooling pumps deleted f rom the IST program?
CEC 0's Response: The spent fuel cooling pumps do not mitigate the consequence of an accident or perform a function in shutting down the reactor. Also these pumps are not supplied with an emergency power source. The safety grade service water system is available for make-up to the spent fuel pool.
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ATTACHMENT 2
3 Attachment #2 Page Changes 2 Table of Contents revised to reflect changes to IST Program.
170 Under ' Pumps', Table 4.2 lists all pumps to be tested.
Section 4.2.1 is the pertinent pump positions. Section 4.2.2 is the pertinent relief requests.
i 172 Typo fixed in 3.a 173 Title changed to Zion Pump Table 4.2. Diff. Press. and Flowrate changed to P-6 for CC pumps.~ Out. Press. changed to 'yes' for CC pump, OCC005. Speed changed to 'yes' for Aux FW pump, FWOO4.
174 Title changed to Zion Pump Table 4.2. Speed changed to 'yes' for CS pump, CS003. Inlet Press changed to 'PR-6' for D0 pumps.
174a Last sentence was rewritten.
174b An additional paragraph added at the end.
174f ' Differential pressure' is changed to ' discharge pressure' in the first sentence.
174g Add Pump Position #6 176 Puinp Relief #1 has' been withdrawn.
177 Paragraphs 3 and 4 have been expanded to include additional information.
180a An additional sentence has been added to the end of paragraph 1.
180c Pump Relief #6 has been revised.
180d Pump Relief #7 has been withdrawn.
180e Pump Relief #8 has been withdrawn.
186 Add backflow testing (reverse flow) and remove 'VR-26' for service water pump discharge check valves.
187 Add valves OMOV-SWOOO9 and OMOV-SWOO10. Remove 'D-5' from U2 drawing location.
188b Remove 'VR-30' and ' Partial Stroked Quarterly' f rom D00055, 56, 65, 66 and 0000025, 26. Add additional statement in Remarks for diesel generator air start check valves.
189 Add maximum stroke time of 60 sec and VR-32 to LCV-lW01, 2 and PCV-lWO3.
190a Add valve FCV-FP08.
191 Change MOV-CS0002, 4, 6 to Category B, remove LRJ testing and remove
' VR-13, 28 ' . Change C50005, 9,13 to Category A, add LRJ testing and
! add ' VR-13' .
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Page Corrections ,
194 Change maximum stroke the'of PCV-4%t,356 to 8 thys. Add valve ]
RC-8045. t 196 Add back flow test requirements for VC8481 A, B and VC8542 A, B. ,,
i 1 197 Change MOV-RH8701, 2 to Category A. Remove ' VR-4 ' \nd add P-17 ' f or '
RH8730A, B. Change RH8736A, B and RH8949A, B to Cdtegory A/C. <
199 Change S18905 A,'5 to Ca;egory A/C. Change test frecuency to 'BR' for 518912. ; y 200 Change S190040, 0 and S19012A, B, C, D to Category A/C. S18949C,0 will be leak test'ed as a PlV and will be categorized as A/C.
201 Add 'VR-13' to A0V-518880. Change S18948A, B, C, 0, S18956A, B, C, D and S19001A to Category A/C. Add 'P-18' to S19001 A and change frequency to 'EC'. ,
202 Change S19001B, C, D and S19002A, B, C, D to Category A/C, add
'P-18', change f requency to 'EC' . Remove 'VR-25' from S19002A, B, C, D. Add 'VR-13', remove LRJ testing and change to Category A/C for .
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203 Add A0V-CC9437. Add back fIcv requirements 'and Position #20 to CC9463A, B and.0CCS464.
206 Change 'VR-14' to 'VP.-13' f or PR00E9, 30. g"hange PR0029 to Catagory A/C. Change, WR-2' to 'VR-13' f or FCV-PR24A, ih -
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206a Add 'VR-13' to 50V DR25A, B, C, D and 50V PR26A, 8, C, D.
208 Change 'VR-22' to 'P-19, VR-13' and change f requtncy to 'EC' f or FCV-1A01A, B. /
211 Add VR-13 to DT-9157. Add valve DT9138.
212 Add VR-13 to A0V-RV0001, 2, 3, 4.
212a Last sentence of paragraph 2 has be(n veised.
212e Valve Position #10,12 are withdrawn 212f Add Valve Position #17. *
- 212g Add Va lve Positions #18,19, 20, 21.
215 Revised Valve Relief #2 to inciude' red'ef f rom leak test trending.
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216 Remove FCV-PR24 A, B f rorn list.
222 Valve Relief #4 has been withdrawn. ,
223 Valve Relief #5 has been revised. ,
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l' Page Corrections .;.
227 Valve Relief #9 has been revised .
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232 Valve Relief #13 has been. revised to include' e d valves which are { p Type 'C' leak tested.
i List of Type C leak tested valves.
232a -]
'l 233 i Valve Reliei #14 has been. withdrawn. ,
ij i
234a Valve Relief #16 has been expanded. I 234h Valve Relief #21 has been revised, l l 234i Valve Relief #22 has been withdrawn.
234j Va'Ive Relief #23 has been revised. 6 2341 Valve Relief #25 has been withdrawn.
234n The test f requency is changed to cold' shutdown.
1 2340 Valve Relief #28 has been withdrawn.
5 234q' Valve Relief #30 has been withdrawn. ';
Add Valve Relief #32.
234s .
234t Blank page. ,
234u Page-shifted from 234s.
234y Page shif ted from JJt 234z Page shifted from 234z.
\
F
! 1019t 1 0459A
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ATTACHMENT 3
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Attachment #3 Revised Pages Including Additional Positions, Relief Requests and Additions to the Zion Generating Station Units 1 and 2 Inservice Inspection Program for the Second Ten Year Interval, Rev. 5 ,
i Pages ,
2 186 208 233
[
170 187 211 234a 172 188b 212 234h 173 189 212a 234i 174 190a 212e 234j j 174a 191 212f 2341 174b 194 212g 234n 174f 196 215 2340 1749 197 216 234q 176 199 222 234s 177 200 223 234t 180a 201 227 234u 180c 202 232 234y f 180d 203 232a 234z 180e 206 233 206a 10191 0459A
T ZION UNITS #1 and #2 TABLE OF CONTENTS SECTION .ITEN PAGE 1.0 Introduction 3 1.1 General 3
^1. 2 Management 3 i
1.3 System Classification 4 1.4 Component Construction Tables 5-9 2.0 Inspection Program 10 2.1 Description 10-11 2.2- IWB - Tables 12-31 2.2.1 IWB - Figures. 32-51 2.3 IWC - Tables 52-59 2.3.1 IWC - Figures 60-70 2.4 IWD - 7 ables 71-74
.2.4.1 IWD - Figures 75-78 .
2.5 IWF - Tables 79-81 2.5.1 IWF - Figures 82-87 3.0 Program Positions & Reliefs 88 3.1 Positions89-112 3.2 IWB Reliefs 113-126 3.3 IWC Reliefs 127-134 3.4 Hydrostatic Test Reliefs 135-141d 3.4.A Hydro Relief Attachments 142-168k-4.0 7est Program 169 4.1 - Description 170 4.2 IWP - Tables 171-174 4.2.1 IWP Positions 174a-1749 4.2.2 IWP Reliefs 175-180e 4.3 IWV - Tables 181-212 4.3.1 IWV Positions 212a-2129 4.3.2 IWV Reliefs 213-234t 4.3.A Valve Relief Attachment 234u-234z L 5.0 Amended Technical 5 specifications 235 5.1 General 236 5.2 5tructura l. Integrity 237 5.3 Steam Generators 248 5.4 Valves 261 5.5 5nubbers 263 5.6 Reports 269 6.0 Zion Station section XI P&ID's 272 2
1019t 0459A
l !
, , , . e 4.0 Test Programs t
5.
l t
t l
169 1019t 0459A
_____-____-__a
I 4.0 Test Programs 4,1 Description .)
The Inservice Testing Program for Pumps and Valves meets the ,
requirements and intent of the A.S.M.E. Boiler and Pressure Vessel Code,: Section XI 1980 Edition thru Winter 1981 Addenda for the 2nd l' Interval.
It-is the aim of the station to meet section XI requirements to the extent practical and assure safety and operational readiness is t maintained at the highest achievable level. Where new testing techniques are developed which would extend our present capabilities, {
these will be reviewed and may be incorporated into the testing programs where applicable. Where the section XI requirements are determined to be impractical specific requests for relief are included in this program.
These programs are presented in a tabular fermat as follows:
Pumps Table 4.2 lists all . pumps to be tested, all parameters to be ll measured, pump positions, specific relief requests where they are necessary and a table description.
Section 4.2.1 is the pertinent pump positions. Section 4.2.2 is the {l-pertinent relief requests. It should be noted that pump speed is not a measured quantity for induction constant speed motor-driven pumps, per IWP-3100. y Valves
'4.3 lists all valves which have been assigned a specific category per IWV. The tables are organized by system and follow the numerical order of the station M prints.
4.3.1 are the applicable valve positions. 4.3.2 are the applicable relief requests.
All pumps and valves in these sections were classified and tests determined per the code. However should certain A.S.M.E.Section XI Code requirements be discovered impractical due to unforeseen reasons during the testing process, relief will be requested from that specific code requirement at that time. It has been concluded by the station per the requirements of 10CFR50.59 that this program does not reduce the safety of the plant nor does it place the plant in an unsafe condition.
1 l
170 4
1019t 0459A
4.2-IWP - Tables i
171 1019t 0459A
__-___-_--_- _ ~
4 e e ..
- Table Description
- 1. Pump Number
- a. Numbers preceded by "0" indicate pumps common to both unit one and unit two.
- b. Unless preceded by "1" (Unit 1), "2" (Unit 2) or "0" (both U units), pump numbers are identical for Unit i and Unit 2 and are ,.
preceded by the unit number for use. :
- 2. Class
- a. Numbers 1, 2 and 3 indicate ASME Code Class '
- 3. Test Parameters
- a. Are listed on Table 4.2 required by ASME 5ection XI. g
- b. Interpretation
- 1. N/A, not applicable for testing this parameter.
- 2. Parameters marked with a (yes) can be measured during ;
testing intervai. I
- 3. Parameters marked with P-1, P-2 etc. reference pump position! in 5e: tion 4.2.1.
- 4. Parameters marked with PR-1, 2 etc. reference pump relief requests in Section 4.2.2.
0 i
i l
l 172 l-10191 !
i 0459A
U e e / / e e e e e e e e e e L Y Y N N Y Y Y Y Y Y Y Y Y Y 2
4 4 4 4 4 4 4 4 4 4 n G - - A A - - - - - - - - s s o R R R / / R R R R R R R R e e i B P P N N P P P P P P P P Y Y s
7i v e .
R R 3 3 3 3 3 3 3 3 3 3 3 3 3 3 B - - - - - - - - - - - - - -
I R R R R R R R R R R R R R R V P P P P P P P P P P P P P P WE s s s s 2 2 2 OT e e e e 6 6 6 6 6 - - - s s LA Y Y Y Y - - - - - R R R e e FR P P P P P P P P Y Y S
R E
T FS s s s s 2 2 2 E FS e e e e 6 6 6 6 6 - - - s s M I E Y Y Y Y - - - - - R R R e e A DR P P P P P P P P Y Y R P A
P TS T ES 2 2 2 S LE s s s s s s s s s - - - s s m E TR e e e e e e e e e R R R e e 2 a T UP Y Y Y Y Y Y Y Y Y P P P Y Y r O g
4 o 2
~
E r L P d TS 2 2 2 B n ES s s s s s s s s s - - - s s t LE e e e e e e e e e R R R e e A
T s a NR Y Y Y Y Y Y Y Y Y P P P Y Y e 1 I P P T M s U e t D P c i E A A A A A A A A A A A A s A i
n N v r U E / / / / / / / / / / / / e /
O P N N N N N N N N N N N N Y N I e S Z s n
I S
S A 2 2 2 2 3 3 3 3 3 3 3 3 3 3 L
C
) ) )
R R r H H o R R t
( ( ) ) ) ) ) o l l W
C W
C W
C W
C W
C M
(
a a C C C C C v v ( ( ( ( ( r r o o ) ) ) e e m m e
g n
g g n
g n
g W W W t t a
e n n S S S a E ) ) R R i i i i i ( ( ( w w M I I l l l l l d d A S S t t o o o o o r r r e e N H H a a o o o o o e e e e e H H e e C C C C C t t t F F P ( ( H H a a a M
U g g l l t
n t
n t
n t
n t
n W W W y) re y
r P n n a a e e e e e e e e an a i i u u n n n n n c c c ii i g g d d o o o o o i i i l b l r r i i p p p p p v v v i r i a a s s m m m m m r r r xu x h h e e o o o o o e e e uT u C C R R C C C C C S S S A( A 3 4 5 6 7 4 5
. 6 7 1 2 0 0 0 0 0 1 2 3 0 0 PT 0 0 0 0 0 0 0 0 0 0 O 0 0 0 MN 0 0 0 0 C C C C C O O 0 - -
UE C C H H C C C C C W W W W W PD V V R R O O D O O S S S F F I
/ U e e e e e / / / / / /
0 L Y Y Y Y Y N N N N N N 1
1 4 4 4 4 4 4 4 4 4 4 4 e G - - - - - - - - - - -
t R R R R R R R R R R R R a B P P P P P P P P P P P D
?
2 R 3 3 3 3 3 3 3 3 3 3 3 B - - - - - - - - - - -
I R R R R R R R R R R R n V P P P P P P P P P P P o
i s
i WE s s s s s 6 6 6 6 6 6 v "
OT e e e e e - - - - - -
e LA Y Y Y Y Y R R R R R R R FR P P P P P P S
R l E
T FS s s s s s 6 6 6 6 6 6 E FS e e e e e - - - - - -
M I E Y Y Y Y Y R R R R R R A DR P P P P P P R P A
P TS T ES S LE s s s s s s s s s s s m E TR e e e e e e e e e e e 2 a T UP Y Y Y Y Y Y Y Y Y Y Y r D g
4 2 o
E P
r#
L d TS 6 6 6 6 6 6 B n ES s s s s s - - - - - -
t LE e e e e e R R R R R R A
T s a NR Y Y Y Y Y P P P P P P e 1 I P P T #
M U e s P c t D i
i E A A s A A A A A A A A N v E / / e / / / / / / / /
O r n P N N Y N N N N N N N N I e U S Z s n
I S
S A A A A A A A 2 2 2 2 2 / / / / / /
L N N N N N N C
D I
) ) ) ) )
S S S S S C C C I I
( ( ( S S
( (
y y y a a a n n E r r r o o ) ) ) ) ) )
M p p p i i O O O O 0 0 A S S S t t D D D D 0 0 N c c ( ( ( ( ( (
t t t e e P n n n j j l l l l l l M e e e n n i i i i i i U m m m I I O O O O O O P n n n i i i y y l l l l l l a a a t t e e e e e e t t t e e s s s s s s n n n f f e e e e e e o o o a a i i i i i i C C C S S D D D D D D 3 4
. 1 2 3 3 4 3 4 5 6 0 0 PT 0 0 0 0 0 0 0 0 0 0 0 MN 0 0 0 0 0 0 0 0 0 0 0 UE S S S I 1 0 0 0 0 D D PD C C C S S D D D D O 0 I
l 4.2.1 l IWP - Positions !
l In this section it is the station's intent to specify with respect to ASME Section XI applicability, interpretation, and specifics relevant to this .
station. It is not the station's purpose'or intent to minimize the ;
requirements but to meet the code intent to the fullest. This at times !
requires a clarification due to vagueness in certain areas and specifics, when j examinations are required on components with built in construction e restrictions.
The following Positions apply strictly to the station and are intended to clarify interpretation of the code for both the station and authorities.
Zion's. Positions are general and specific. Where a strict-reading of the ASME .
requirements yields insufficient guidance to implement the Code at Zion Station, the Zion's stated Positions will be utilized as clarification and will define the Station's interpretation of the Code.
(
1 174a 1019t 0459A
Pump Position il It is the station's position that the manufacturer's pump performance curves consisting of multiple data points shall be used for reference values as allowed by IWP-3110 for all pumps included in the IST Pump Program except the diesel generator oil transfer pumps. These represent the pump's design or optimum performance curves. The curves are generated at the factory with design pump clearances under controlled conditions with instrumentation of better accuracies than instruments normally installed in the field.
In addition per. IWP-3210, the Owner has specified reduced limits of i 10%
of the manufacturer's curves as opposed to the limits in Table 3100-2. Where lion Station-tests at an increased f requency, alert ranges except on vibration readings will not be used since the required action is to increase frequency and this is already done. If an adverse trend is identified, the cause of the deviation or condition will be corrected.
Zion currently does meet the code requirements of Table 3100-2 on the low end of the action range. However, on the high end, the Code states a limit of
+3% and Zion's upper limit as stated in the Technical Specifications is +10%.
~
The industry has already identified that the +3% upper limit is too restrictive and has increased the limit to +10% in OH-6 Document, Draf t 8.
Degradation of.a pump is represented by a decrease in performance, not an increase. The upper limit normally accounts for system instrument inaccuracy and does not represent degradation. It's purpose is to identify faulty instrumentation. In order to be consistent with the Zion Technical Specifications, i 10% of the manufacturer's pump curve will be used as criteria for pump operability.
174b i 1019t 0459A
c:
Pump Position #2-l It is the station's position that for pumps without bearings on the pump end, the: requirement to measure bearing temperature is not applicable. This is the case for the residual heat removal pumps.
-i 174c 1019t
-0459A
i Pump Position T:
It is the station's position that any pump already running during normal' !
cperation need not be. secured to determine the initial suction pressure of the {
. pump before start per ASME Boiler and Pressure Vessel Code Section XI .i (IWP-3400(b)). In this case, the suction pressure will only be taken while '!'
pump is running.
174d
-1019t 0459A
- - - _-_-__ ____ - ___ a
,, g ,. .
l 1
J Pump Position #4 1
1 It is the Station's position that flow and differential pressure .
{
measurements for the Component Cooling Pumps 0C0003 thru 000007 will be taken - 'j at quarterly intervals as allowed by the ASME code. Operability tests to I
-insure adequate cooling throughout the plant and vibration measurements will continue to be performed monthly. Due to system design and accuracy requirements, ultrasonic flow instruments were installed. To use this type of instrumentation requires the coordination of three dif ferent departments and excessive paperwork and time commitment. In view of this, lion Station will perform flow and differential pressure measurements quarterly and will implement both alert and action ranges into the test procedure. When a pump exc'eeds the alert range testing will be increased to monthly as required by the ASML Code.
174e
.1019t
-0459A
. c ., o Pump Position #5 It is the position of Zion Station that the diesel generator oil transfer pumps be tested for flow, discharge pressure and vibration at quarterly ll intervals as permitted by the ASME Code. These pumps are tested at least and of ten in excess of monthly for their ability to transfer oil. To minimize the number of starts for these pumps and the work load, the additional test procedure to measure the parameters required by the ASME Code will be performed quarterly. Alert and action ranges will be implemented into the test procedure. When a pump exceeds the alert range, testing will be increased to monthiy as required by the ASME Code.
174f 1019t 0459A
. t. . . . . .
Pump Position #6 As permitted by IWP-3210, Zion Station has increased the limits of the alert range in Table IWP-3100-2 f rom (1.02 to 1.03) APr to (1.07 to 1.10)
APr for Component Cooling Pumps OCC003 thru OCC007. (See Pump Position #1 for justification of an increased upper limit). The range of test parameters are as follows: <
Test' Acceptable Alert Required Parameter Range Ranae Action Range AP 5 1 7% Pump Curve >17% Pump Curve >i10% Pump Curve and 1 110% Pump Curve The action range sha!! remain consistent with Pump Position #1 as greater
-than 110% of the pump curve. The Station will continue to monitor trends below the pump curve which may adversely affect pump performance.
1749 1019t 0459A
C 4.2.2 IWP - Reliefs 175 1019t 0459A
t 5
i ~
Pump Relief #1 Withd rawn (Reference Pump Position #6) 176 l 1019t 0459A
0
- Pump R'e fief #2
- Relief is requested from pressure and flow measurements for Service Water Pumps SW001, 2 and 3.
Code Requirement f
Individually test pump per IWP-3400(a), pressure measurements and flow measurement per IWP-3100.
Basis and Alternate Service water pumps are of vertical design with no means to measure direct inlet pressure. The inlet pressure to these pumps will be established by reference to the level of lake water above pump suction. Measuring inlet pressure with the pump idle is, not necessary because the level in the forbay will not change by an appreciable amount before and after the operation of a service water pump.
[
Individually flow testing each pump at times other than refueling outages would ,
jeopardize safe plant operation and may conflict with the Technical Specifications. [t During refueling outages when it is permissible to run one pump at a time, individual flow measurements will be taken in the common discharge header for each pump. A situation may occur when it is required by the lechnical Specifications that the cross-tie remains open between Unit i and Unit 2 service water systems (i.e., a service water pump is out of service for a major overhaul). The individual flow rates of the pumps cannot be measured while the cross-tie is open since the ,
flow instrumentation is located down stream of the cross-tie. If inis situation i should occur for the duration of the refueling outage, this test will not be .
performed. The flow measurements will be used to calculate a reference dif ferential pressure from the manufacturer's pump curve and this value will be compared to the measured dif ferential pressure to insure that the pump is operating within 110% of the established pump curve. Additional relief may be necessary after data is analyzed from the first inservice test. Flow rate and differential pressure through the. service water pumps vary depending on plant conditions, how many pumps are running and the demand on the system. Therefore consistent reference values cannot be established. Since the measured flow rate is used to determine the reference k differential pressure f rom the pump curve and this is only performed during I refueling outages, the parameters used to calculate differential pressure (i.e.
inlet and outlet pressures) will also be measured only at refueling outages. It is impractical and meaningless to take measurements that cannot be compared to a '
reference value.
Past plant design did not incorporate individual pump discharge flow ,
instrumentation. Currently there is no flow instrumentation that can be installed near the pump to measure individual flow quarterly because of insufficient straight :
length pipe which is needed for accurate flow measurements. Flow instrumentation '
was installed in the common discharge header because it is the closest area near the pump with sufficient straight length pipe to install accurate flow instrumentation.
The first test was to be run on U-1 during the 1986 refueling outage. However, the ;
flow instrumentation did not perform properly and could not be repaired. Zion Station is currently investigating three new methods to measure flow. Zion Station i proposes to install new flow instrumentation on Units 1 and 2 during their next ;
scheduled refueling outages in 1988. I As required by Zion's Technical Specifications, a monthly operational test is performed to insure that the pumps are providing adequate cooling throughout the plant. Vibration readings and discharga pressure are also measured during this monthly operational test. This alternative will provide adequate assurance of ll continued operational readiness.
177 1019t 0459A
_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ __ a
_ _ _ - _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - - _ _ _ - _ _ _ - _ _ _ _ _ _ _
e e s , ,
Pump Relief f3 Relief is requested f rom ASME.Section XI Subsections IWP-4510, 3110, 3100 and 4520 for vibration measurements only.
Code Requirement Vibration testing per ASME Section XI Subsections IWP-4510, 3110, 3100 and 4520. .
Basis and Alternative Relief is requested to use Zion's vibration program as it relates to the I following subsections: l
- 1) IWP-4510 Vibration Amplitude A significant improvement in the predictive capability of Vibration l Monitoring can be achieved by measuring vibration velocity (rms) in place of vibration displacement. This thought is commonly shared i throughout the industry and by ASME. [ Reference A5ME publication '
18-WA/NE-5 and International l Standard 150 2312-1974(E).]
- 2) IWP-3110 Reference Values Reference values for the purpose of establishing vibration acceptance levels are undesirable. Properly maintained and balanced equipment may result in very low reference values. Minor variations could then result in unnecessary inspections which adversely affect equipment ,
availability. In addition equipment with high referente values may ]
be permitted to operate at levels which may result in pump l degradation and damage. l The Zion program is designed to monitor vibration trends. All vibration monitoring data is trended and the data is used as guidelines for scheduled preventative maintenance usually during routine outages. Trending, independent of absolute levels, is the key to the Zion program.
- 3) IWP-3100 Inservice Test Procedure Currently the use of the allowable vibration ranges listed in Table :
IWP-3100-2 do not protect Zion's equipment adequately. As stated previously, equipment with high reference levels may be permitted to operate at levels which may result in pump degradation and damage.
l i
178 i.
l.
1019t l
10459A 1
7 11
!I y
Zion believes that vibration limits based solely on general vibration' ;
severity charts are not adequate in that they do not consider variations.in vibrational characteristics of equipment of varying ;
design and purpose (eg., diesels, motors, fans, pumps, turbines etc.).
In a field where there is very little solid and specific infornetion q on-limits, it is preferable to use the most specific information 4 available for determination of limits. Eleven years of experience at l Zion Station indicates that the most appropriate limits are those '
that allmd for variations in equipment design. Therefore, for the purpose of establishing limits, use of the following is proposed:
A) Canadian Government Specification CDA/MS/NU5H 107:
Vibration Limits for Maintenance.
B) Specific limits from pump manuf acturers if more limiting than CDA/MS/NUCH 107.
C) Historical data that indicates a more limiting value is necessary.
4 Any changes to the specific limits adopted will have to go through an On-Site Review and no change above the CDA/MS/NUSH 107 limit of 10 _
mm/sec rms " alert range" and 18 mm/sec action range shall be l authorized. The Zion program not only has the advantage of being 4 equipment specific but also requires adoption of lower limits should it become evident the current limits are not providing adequate '
protection. In_ addition it is important to emphasize that corrective action will usually be taken prior to alert ranges being reached based on attention to data trending.
As previously stated, the Zion pump vibration program is designed to l monitor trends. However, all vibration values and other code required parameters are measured in accordance with the procedure delineated in IWP-3100 to~ assure that repeatability of testing ;
conditions is maintained. l
- 4) IWP-3230 Corrective Action With the exception of the diesel generator oil transfer pumps, the present Zion program exceeds the testing f requency requirements of IWP-3230 when vibration levels reach the " Alert Range". The program calls for vibration readings to be taken on a monthly basis when equipment is required operable. In addition if a particular piece of equipment does reach alert level and is running continuously the vibration data is taken at twice the frequency. The above permits accurate trending and appropriate scheduling of maintenance.
If deviations should reach-the required action range, corrective action will be as per IWP-3230.
178a 1019t 0459A
f
- 5) IWP-4520 Instrument to Measure Amplitude ,
The frequency response range of Zion's vibration monitoring equipment ,
is - linear f rom 10 to 10K hertz. This exceeds the requirements of '
IWP-4520 with the exception that accurate measurement can only be obtained down to 80% of running speed on the service water pumps.
Based on vibration analysis history on the service water pumps, the lowest frequency has been structural resonance which occurred at 11 !
hertz, which is within the frequency response range of Zion's vibration monitoring equipment. It is felt that Zion's present state of the art monitoring equipment provides all the data necessary to safeguard this equipment.
}
This relief as proposed will provide adequate assurance that operational readiness and safety will be maintained at the plant. [
178b 1019t 0459A
. o .. .
- i Bearing Measurements From
- Canadian Government Specification CDA/MS/NUSH 107: Vibration Limits for Maintenance 1"/sec = 25.38 mm/sec 1 mm/sec = .0394"/sec Limits for equipment Level 3 Level 4 Level 3 Level 4 Turbine 18mm/sec 32mm/sec .709"/sec 1.26"/sec i
- Small Turbine 10mm/sec 18mm/sec .394"/sec .709"/sec 4 Compressors 10mm/sec 18mm/sec .394"/sec .709"/sec Diesel Generators 18mm/sec 32mm/sec .709"/sec 1.26"/sec MG Sets 5.6mm/sec 10mm/sec .22"/sec .394"/sec Pumps 10mm/sec 18mm/sec .394"/sec .709"/sec Fans 5.6mm/sec 10mm/sec .22"/sec .394"/sec E lectric ' Mtrs . 3.2mm/sec 5.6mm/sec .126"/ste .22"/sec 0 Level 3 - Service is called for .314"/sec 0 Level 4 - Repair Immediately .628"/sec 179 1019t 0459A
w ooo Ev e siwai ng e a meen.ac's cens VDI2055 _~~ sea mes m))
150 2372 en -he n ein re .nte.maien ;a n:3 . a. BS4575 e bla. A trDical s a ample is ' the C,erma n __
Set the 251 *.! 10 menure sew.terity) g Mard VDI 205 6. *lhe vibransn empli.
81 the machine dweing smooth oper. * ~ -
allin es n' be Ia k e n a s as " good
- cla s sili.:
44 0 pg f .
26..*f he criteria shown suggtsu that A**"*"**
. ~cssswe *
- vibestion inesesses of about . ,
185 18 % ,,
2,5 }irnss ,111 move the vibra,ilon condi. % ,,
1*,on ,f ram "pood", to *' allowable", to just } 3,3, ,9 ,
p,..
181arabl3 ", to "nos permissible". ,,
- m. .= 7,1 -
kn sei.e.bi.
The ' gibration Seeerhy, fres;uer cy tange ~
" 3 '*" ;
eacas bt 1000 Ht. High meshing isenven. 4
~
I Glas., blat'e . resonances, tuobing a nci m. I 2J --
8 #' t' ##3
- Me I
Oerly beating failure detection requires a {-
[125 g 2A j
c*.dar lesquency ra nge se mo,re feli4ble E Am aae Cesubs 3-era usually obtained' by merca. ea w
upper . Isequency Em'st so C.the so Hz. ! 117 D,71 W g, g 1
Ph2 table below shcrws an estract.froris 113 a 0.45 - , ,w ,. 7 <
u,g;,,,,. , ,,g.w m,i;w. n.,
u.,e - % i lht Cassdian Goestnment spedfecation ' 33 rs awe e,e se nser esse -en !
a .. => t, w-irr
- 6**' '""* M
~ M '**Eh*Y. *+ XC ' W** ***d*' -
EDA./M5/NVSH 107. This si es values *
. ics D,i s
- "***'**Y DI eccepsable I;mhs of bearing 'v,ibraliott* O'**'"
e? a number of chfierent machin'el types. _
I l O'"'" '! E'*"' O !
- f TABLE'OF' CRITERIA - BEARING.M MEASUREMENTS {101 rom Canadian Governrnent Specification CDA/MS/NV5H 107: 10 000'Hz)
Vibrati6n Umits'for i
M Sei the 2513 to sneasure Lin.(ear)
FOR NEYr M AD.HINEs
- 7 ' ** F OR Wo' RN MACHINES "Y (Iwil spe,d Ei po ar) ' FOR NEW MADMINEs FOR WORN MADMIN@
W * * **W3 so . te,,the I.Das life' I Short 3;f,2 welocity RMS Ituli speed 8 po .act)
ICNeck Reca,ng.g; n Do. -;ay . , g, g,,g,ng 3;s,s short 1;t,2 Ched Aeco*40 Is a condition) to new (Oct p=c.h* Par i"reec leve@ g4q l'e con dit'.on) to ne=* (@
anal ys*u)4 gg Vd8' mm/s level 3 * ^*I Y ,
S*1E VdE
- mm/s VdS
- mm/s Vd8
- mm/s
~ 'Vd B *mm/s Vd B
- mes/s Vd8
- mm/s Vdg
- mer b:et 70.000 HP)' 138 7.9 145 18 boilers l Aus.) .120 1,0 130 33 .135. 5.5' 145 18 150*32 1 140 1D O 13 20.000 HP') 128 2.5 135 - 5,6 esp 1a 5.000 HP) 140 .10 145 18
- 118 D,79 130 32 135 120 1.0 5.6 140, 10 130 33 ^
135 5.6 ifD 10 per 20.000 HP) 125 it 145 1B s
145 18 150 22 r 5 HP) 123 1,4 135 5,6 14D 10 145 18 3 io 20 000 HPl 120 1.0 135 5.6 145 18 15D 22 Ivo to 5 HPJ 118 0.79 130 33 135 5.6 140 10 so to 5.000 HPJ ' 115 0.56 130 3J 140 10 145 13 Fam Ice 4o 1800 rpm) 120 1.D 130 .3.2 r ><ston) 14D 10 135 5.5 140 10 15D 32 15D 32 '155 56 i
labove 12CD rom). 115 0.56 130 32 ~135 53 w air. e;< cond.)
a 133 140 1D 4.5 14D 10 140 10
[P eir1 123 145 18 Ewcsric Mosen As;dre)
'1,4 125 53 140 1D 445 18 115 D.56 (c m 5 HP or be-125 . 5.6 14D 10 145 18 to- 1200 rpm) 105 0.35 125 1,8 130 3J 135 1,4 So
=41 Ge erasen l 123 l 140 10 l 145 18 Ivoto5 HPcw l150 32
>as e Ay, ate ,1200 tpm) 1C3 0,14 125 1,8 130 3.2 135 Sc 3 3.e***a s sars l23 l1 1,4 14D 10 145 18 15D 22 H'" *"'
- b** (o er 1 k val 103 0.14 - -
115 D.56 120 h-de 10.000 HP) 170 1D 140 10 11 h V A or below) '1 00 0,10 110 115 145 18 iSD 32 0.32 De B so 10 CCD HP) 115 0.56 135 5.5 145 e 15 15D 32 91810 WJ 110 DJ2 130 33 -
14D 10 145 18
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180
1 e , ,, ,
Pump Relief #4
' Relief is requested from taking pump bearing temperature as specified in IWP-3100,1WP-3300, IWP-3500(b),1WP-4310 and IWP-6230 f or. the charging pumps, component cooling pumps, containment spray pumps, safety injection pumps, i
service water pumps and the diesel generator oil transfer pumps.
Code Requirement l-
- Measuring and recording bearing temperatures of pumps per 1WP-3100, 3300 3500(b), 4310 and 6230 during one inservice test each year. ,
Basis and Alternative These pumps were not designed to permit pump bearing temperature measurements. They are not provided with permanent temperature detectors or thermal wells. A test was performed in which a thermocouple couple was attached to the outside of the bearing housing. It was found that the temperatures obtained reflected the ambient temperature more than the actual bearing temperature. Therefore, gathering meaningful data on bearing temperatures is: impractical. Furthermore, bearing temperature measurement will not provide significant additional information regarding bearing condition than is already obtained through vibration monitoring. An increase in bearing temperature usually occurs when the bearing has already degraded to a point indicative to pump failure. Vibration data better detects developing problems before the degradation of pump and provides more concise information with respect to the pump and bearing condition. Vibration data can provide information as to the change in the balance of rotating parts, misalignment of bearings, worn bearings, changes in internal hydraulic forces and general pump integrity. Vibration tests are taken at least quarterly, whereas bearing temperature is only taken annually. Therefore, vibration velocity measurements will be-taken in lieu of bearing temperatures to monitor for pump degradation.
This alternative will provide adequate assurance of continued operational readiness and should increase pump longevity by detecting possible problems at an earlier stage.
180a 1019t.
0459A
_ _ - _ - _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
PumD Relief f5 Relief is requested f rom the range requirements for electronic digital
. instruments as specified in IWP-4120.
Code Requirements IWP-4120 (Range).
Basis and Alternative At Zion Station all installed instrumentation such as gages for pressure and flow measurements meet the requirements for calibration, accuracy and range except where specific relief has been requested.
Zion Station requests relief for electronic digital instrumentation f rom the requirement that the full-scale range of the instrument shall be three times the reference value or less. ' Electronic digital instruments meet the required accuracies at both the high and low sides of their range. Therefore accuracy is independent of the instrument's range. The range of a dial instrument is most important when an operator is judging what the actual value is, using the scale provided on the instrument. If this scale is too large the accuracy of the operator's reading will greatly decrease. Since a digital instrument only displays one value, there will be no additional operator judgement error that will decrease the accuracy of the instrument.
Zion Station proposes that all electronic digital instruments used for testing equipment will meet the calibration and accuracy requirements throughout its range but will be exempt from the range requirements of Section XI. This alternative will provide adequate assurance of the required level of safety and that operational readiness is maintained.
I I
l 180b 1019t 0459A
P/ F y~ , s .s .
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Pump Relief #6 . ,
Relief is requested f rom the reference value and alert range requirements for ll the diesel generator oil transfer pumps. '
- s ' '
a 4 y.
Code Requirement j
- IWP-3110 (Reference Values) and IWPl3210 ( Allowable Ranges). ll
(
Basis and Alternative l Relief is requested f rom $ establishing reference valths for and measuring -'
suction pressure and differential pressure for tha dieteI transfer pumps.
These pumps are positive displacement pumps so therefore flow and pressure are independent variables. Discharge pressure and flow rate are the only parameters necessary to determine pump condition. '
-Relief is also requested from the alert range requireme' hts for the diesel ll
. generator oil transfer pumps. These pumps are very low capacity pumps with a f low rate of approximately 7-9 GPM. Due to instrument accuracy, it would be ll impossible to meet the range requirements of the ASME Code when the measured parameters are so small. Therefore Zion Station has generated its own alert and action ranges which have been based on the requirements of the Zion Technical Specifications, data f r9en periodEtests and the manuf acturer's >
recommendations. The ranges will 'be as follows: "-
~
v/Q 7
Acceptable ':: Alert- Action Pump Capacity > 6.5 gpm < 6.5 gpm 5 6.0 gpm Pump Out. Press. 9 to 30 psig < 9 psig,
$ '8 psig ll Vibration < 8 mm/sec > 8mm/sec > 12 mm/sec 5 /
This alternative will provide adequate assurance of' continued operational' readiness. ,
s i
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I' IWV-Tables i
181 1019t 0459A
__ ________-_____a .
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Table Description i
A. Title Block Area
- 1. System Name- ,
- 2. Drawing Number (P & 10) i
- 3. -Unit Number
'4. Date of last revision / issue -
I
- 5. Page number B. Table
- 1 ~. Valve nuraber
- a. Numbers preceded by 'O' indicate valves common to both unit one l and unit two. L t
- b. unless preceded by "l* (Unit 1), "2" (Unit 2) or '0" (Both ' i Units), valve numbers are identical for Unit 1 and Unit 2 and j are preceded by the unit number for use.
- 2. Code Class 3
- a. numbers 1, 2 and 3 indicate ASME Code Class
- b. "NA" indicates valves which are not assigned an ASME Code Class' h' but are considered Faii Safe valves and are included in this program for testing purpcses.
- 3. Valve Category
- a. denotes the category assigned to each valve per Subsection IWV-2000 ,
.i
- 4. Valve Size
- a. lists the nominal size of the valve in inches
- 5. Valve Type a, the following abbreviations indicate valve type G - Gate Gb - Globe B - Butterfly C - Check 5 - Safety R - Relief 0 - Diaphragm 50 - Solenoid A - Angle N - Needle
- b. PIV - Pressure Isolation Valve.
- 6. Actuator Type
- a. the following abbreviations indicate valve actuator type MO - Motor Operated M - Manual AO - Air Operated 5 - 5 elf Actuated H0 - Hydraulic Operated 182
~ 1019t 0459A
... . .. . , . . a
- 7. Test
- a. the tests performed on each valve are abbreviated by the following: ,
t.
- 1. first letter E - Exercise Test 4 L - Leak Test-B - Backflow Test or Disassemble and Inspect
- 2. second letter Q - Quarterly R - Refueling Outage -
~R2 Refueling while Reactor Vessel Head is Removed 1 - As defined'by IWV-3510 C - Cold Shutdown i C1 - Cold Shutdown, no gg. j Reactor Coolant Pumps Operating i C3 - Cold Shutdown, 1 Feedwater and Condensate systems not operating F - Once Every 5 fears
- 3. third letter J - denotes 10CFR50 Appendix J testing
- 4. a' slash "/" divides tests if more than one test is applicable
- 5. a frequency code of "C", "C1 ", "C 3", "R", "R2 "
indicates valves which cannot be full stroked as required by IWV-3412 or IWV-3522 as applicable. (see relief listed for specific information on "C, 1, 3" and "R, R2 "
valves)
- 8. Maximum Stroke Time
- a. time in seconds 9.- Relief Request
- a. indicates the valve relief number which identifies a specific relief request.
- 10. Valve Position
- a. indicates the station's position which identifies why the valves are stroke during all cold shutdowns and not fuil stroked quarterly per the ASME code.
- 11. Passive Valve
- a. indicates a valve which is not required to change position to accompli >n a specific function.
183
'1019t 0459A
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./
0 1 S K
.e R t A a M D E R
2 n
c i
s i
v e L0 CATI 0N 11 1 1 15566337733773333355566444 R - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
DRAWING CBCCCBBBB8BBBBBCC00DDDDDDDDCBB U2 22222 222222222222222 REQUEST 3331 1 11 1 1 1 11 1 1 11 1 1 1 1 RELIEF RRRRR - - - - - - - - - - RRRRRRRRRRRRRRR VVVVV VVVVVVVVVVVVVVV TIME 000 - - 0000000000 - - - - - - - - - - - - - - -
S T STROKE 666 - - 6666666666 - - - - - - - - - - - - - - -
E S V E MAXIMUM L T A
V -
TEST QQQRRQQQQQQQQQQRRRRRRRRRRRRRRR M3 EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE A
RD 2GN OA dR TYPE nP ,
a2 ACTUAT0R 000 0000000000 1S ,
T AAASSAAAAAAAAAASSSSSSSSSSSSSSS E1 9 TT 8 I S 1 NES TYPE UCA GGGCCGGGGGGGGGGCCCCCCCCCCCCCCC IL VALVE NVC OR IEE ZSD NO IC SIZE 2 4442222448888888888888222 11/11/////////////////////////
E VALVE 1 3331111333333333333333111 M
S A
Y R
EO VG C XX XXXXXXXXXXXXXXX LE R AT E VA T C B XXX XXXXXXXXXX
. A W
L A A
E S
E L0 CATI 0N 11 1 1 1 5566337733773333355566444 V - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
L DRAWING CBCCCBBBBBBBBBBCCDDDDDDDDDDCBB A
V U1 N
O CLASS I 2 333333333333333232333333333322 T 1 C0DE A 5 L -
O M 34567891 2345889 S / 1 3 I 2 00 777777788888955 1 2300B901 234567OOO0O0O1 1 1 1 1 1 00 OOO00OO1 1 1 1 1 1 1 1OOO0O0O00000000
- 9 NUMBER WWWWWWWWWWWWWWWWWWWWWWWWWWWWWW II I I I l II I I I I I III I III II I I I II I I I m 3
- - - - - - - - - - - - - tA e -
99 t M VALVE VVV VVVVVVVVVV 1 5 s / CCC CCCCCCCCCC 04 y 1 LLP FFFFFFFFFF 10 S
llllllll
t A a M D E R
1 n
i e
s i
v - -
L0 CATI ON445655633344356641 3542 R - - - - - - - - - - - - - - - - - - - - - -
DRAWI NG BBBBBBBCCCCCDE0D0CFEEB U2 222222222222222222222 REQUEST 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RELI EF RRRRRRRRRRRRRRRRRRRRR -
VVVVVVVVVVVVVVVVVVVVV TI ME S TSTROKE - - - - - - - - - - - - - - - - - - - - - -
E S V EMAXI MUM L T A
V TEST RRRRRRRRRRRRRRRRRRRRRI M3 EEEEEEEEEEEEEEEEEEEEE A
RD 2GN OA dR TYPE nP , .
a 2 ACTUATORSSSSSSSSSSSSSSSSSSSSSS
- T 1 S ,
E1 TT I S NES TYPE UCA CCCCCCCCCCCCCCCCCCCCCR I L VALVE NVC OR I EE ZSD NO IC SI ZE 22222222222222222422B
//////// / / / / // / / // / //1 E VALVE 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 31 13 M
S A
Y R
EO VG CXXXXXXXXXXXXXXXXXXXXXX LE R AT E VA G T C B A
W '
L A A
E S
E L0 CATI ON445655633344356641 3542 V - - - - - - - - - - - - - - - - - - - - - -
L DRAWI NG BBBBBBBCCCCC0E0DDCFEEB A
V U1 N
O CLASS I 2 2233333333333233233333 T 1 C0DE A 5 L -
O M S / 01 234567 890201 23420560 I 2 66666666667 7 8B88869986 OO0000O00OOOOOO001 001 1 OO0000O00OOOOOO 0000000 WWWWWWWWWWWWWWWWWWWWWW
- 9 NUMBER m 3 I I I I I I I I I I I I I I I I I I I I I I e -
t M VALVE s /
y 1 S
,l
_ t A
_ a M E
_ D R
0 n
e i
s i
v
~
a LOCATI ON 5 R -
DRAWING .
B U2 REQUEST RELIEF TI ME 0
TSTR0KE 6 S S E EMAXI MUM V T - .
L A
V TEST Q M E A3 R
2GD ON dRA TYPE nP 0
a , ACTUAT0R A T2 1 S E ,
T T1 I -
NES TYPE UCS G I A VALVE NVL -
ORC I E ZSE
~
ND IO SIZE C 4 VALVE E
M S
A Y
R EO VG C LE AT VA C B X N A O
I T
C E L0 CATI ON 8 T 3 O 1 DRAWI NG A R 5 P - U1 M
E /
R 2 CLASS I '
A F C0DE N 3
4 8 M 0
/ P 1 F
- # NUMBER V m C e . F t g VALVE s w y r S D
t A b n a M f di D E ol el R l l e eib u l
vwmfee eeeeee 3
_ a6 sr vvvvvv v2 s iiiiii
_ n ah ssssss
_ e ed sc ssssss i nnia aaaaaa s Oad e PPPPPP i
v -
0 L0 CATI 0N44434344484B584898489444444 R - - - - - - - - - - - - - - - - - - - - - - - - - - -
DRAWING BCDDFFCEFBBD0F0CCEDFEBBCDEE U2 3 3 3 333333 REQUEST 1 1 1 1 1 1 1 1 1 1 1 1 RELIEF - - - - - - - - - - R - R - RR - R - R - RRRRRR V V VV V V VVVVVV TI ME 000000000 - - - - - - - - - - - - - - - - - -
S TSTROKE 666666222 - - - - - - - - - - - - - - - - - -
E S .
V EMAXIMUM L T J J J A R R R V
TEST QQQQQQQQQQ L, Q L
,Q L,RQRQRQRRRRRR JJJJJJ M3 EEEEEEEEEEQEQEQBEBEBELLLLLL A E E E RD 2GN OA dR TYPE nP , -
a 2 ACTUAT0R00000000 OSSSSSSSSSSSSMMMMMM T MMMMMMMMM 1 S ,
E1 TT I. S NES TYPE UCA GGGGGGGGGCCCCCCCCCCCCGGGGGG I L VALVE NVC OR IEE ZSD NO .
I C SI ZE 00000033300000036363661 61 61 1 1 1 1 1 1 1 1 1 1 1 1 E VALVE M
S
- A Y
- R EO VG C XXXXXXXXXXXX LE R AT E VA T C BXXXXX XXXX A
W L A X X X XXXXXX A
E S
E L0 CATI 0N434343444848584898489444444 V - - - - - - - - - - - - - - - - - - - - - - - - - - -
L DRAWI NG BCDDF FCEF BBDDF0CCEDFEBBC0EE A
V U1 N
O CLASS I 4 222222333222222222222222222 T 1 CODE A 5 L -
O M S / 234567 89035791 3681 3687801 34 I 2 000000001 00001 1 1 1 22223344 4 4 000000000000000000000000000 000000000000000000000000000
- 4 NUMBER SSS5S5S5S55SS5SSSSS55SSSSSS m 4 CCCCCCCCCCCCCCCCCCCCCCCCCCC e - - - - - - - - - -
t M VALVE VVVVVVVVV s / OOOOOOOOO y 1 MMMMMMMMM S
l
) 1! 1l I i){lIllI.jl 1) ii l i lIl 1If 1 1! l, l~1lll
.- ~ - ' -
5 8
9 0
8 o S t K a R D A _
M E
R 1
n t
i s
i v L0 CATION 3333244444444 e - - - - - - - - - - - - - .-
R DRAWING EDBABFEDDCCBA .
U2 REQUEST _
RELIEF - - - - - - - - - - - - -
TIME 0000000000000 S T STROKE 6666666666666 E S V E MAXIMUM L T A
V TEST QQQQQQQQQQQQQ M3 EEEEEEEEEEEEE A
RD 2GN OA dR TYPE nP ,
a 2 ACTUATOR 0000000000000 T AAAAAAAAAAAAA 1 S ,
E1 2 TT 9 I S 1 NES TYPE UCA GGGGGGGGGGGGG IL VALVE NVC OR IEE ZSD NO 88882 IC SIZE /////22222222 33331 E VALVE M 2 S
A Y
R EO VG C LE AT VA N C B XXXXXXXXXXXXX W
O D
W O
A L
B R L0 CATI ON 7777688888888 O - - - - - - - - - - - - -
T DRAWING EDBABFED0CCBA A
R U1 E
N E CLASS G 2222222222222 1 C0DE M -
A 5 E 4 T - 1 2345678 S M 00000000 2345700000000 00O01 00000000
- # NUMBER SSSSD00DDD000 m SSSSB88BBBBBB 1A e . - - - - - - - - - - - - - 99 t g VALVE VVVVVVVVVVVVV 1 5 s w CCCCC0D000000 04 y r FFFFFAAAAAAAA S D ~ 1 0 I' ' l\l l !ll l1jj{
D A M
E R
1 n
e i
s i
v L0 CATI 0N55 -
R DRAWI NG 0D U2 REQ 0EST 22
- ~
REL1 EF RR VV TI ME -
00 S TSTRDKE 66 E S V EMAXIMUM L T -
A JJ V - - RR T E S' T L, L, M3 A QQ RD EE 2GN OA dR TYPE nP ,
a 2 ACTUAT0R00
' T AA lS ,
E1 TT I S '
NES TYPE .
UCA GG I L VALVE NVC OR IEE ZSD NO IC SI ZE 22 E VALVE M
S A
Y R
A AXX S
O P
S I L0 CATI 0N55 - -
D DRAWI NG BB E
T U1 S
A W CLASS 33 D C0DE
. I
_ U 7 Q 4
_ I -
. L M AB
_ .. 77 1 1
_ : NUMBER DD m . WW
_ e .
t g VALVE VV
- D A
- M
- E R
3 n
c i
s i 00000 0 v L0 CATI 0N1 1 11 1 55333 331 R DRAWI NG AAAAAAAAAA AAA U2 9999 REQUEST 2222 1 1 1 1 3
- - - - - - - - - - - - - - 441 RELI EF RRRR - - - - - - RRRR - - -
VVVV VVVVPPR V
TI ME -
00000 - - - 00222288 -
S TSTROKE 66666 - - - 66 E S V EMAXI MUM L T A JJJ J J V RRRRR TEST L L,L,L L,I I I QQ M3 , ,
EE1 1 1 1 CCJ A QQQQQ CCCCEER RD EEEEE EEEE L 2GN OA dR TYPE nP .
a 2 ACTUAT0R00000SSS0Odddd00M T AAAAA MMSSSSAA 1 S ,
E1 TT I S NES TYPE bb bbbb UCA GGDD0RRRGGGGGGD00 I L VALVE NVC OR IEE ZSD NO 88 4 4 I C SI ZE //33/666331 1 1 1 33/
33 3 3 E VALVE M
S A
Y R
EO VG C XXX LE AT VA C B XXXXXXXX AXXXXX X
9 T 65 L0 CATI 0N1 21 2277899 992 N 1 9 - - - - - - - - - - - - - - - - -
A 5 - DRAWI NG AAAAAAAAAA AAA L M O M/ U1 O /2 C 2 CLASS R 6 3333A1 1 1 1 1 1 1 1 1 1 1 A O 35 CODE N N T 59 C - -
A MM E // AB R 1 1 56893 00 22223 00 00000ABC008901 C
- # NUMBER 8888800088001 1 565 m CCCCC1 1 1 CCCCCC554 e . RRRRR000RRRRRR440 t g VALVE - - - - - 888 - - - - - - - - 8 s u VVVVVCCCVVVVVVVV -
y r 00000RRROOO0OOCCC S D AAAAA MMS 5SSPPR l
_ D A M
E R
_ 1 n
t i
s i .
0 - 0 v L0 CATION 6618751 87582 0 .
R DRAWING AAFFFFFFFFAB-U2 -
44444444 2,2,2,2,2,2,2,2, REQUEST 2222222222 RELI EF RRRRRRRRRR - -
VVVVVVVVVV - -
TI ME '
00 - - - - - - - - - -
S TSTROKE 66 - - - - - - - - - -
E S V EMAXI MUM L T JJJJJJJJ A JJRRRRRRRR V R LL R L,L,L,L,L,L,L,L,I TEST I M3 1 1 ) 1 1 jj)
A QQCCCCCCCC RD EEEEEEEEEE 2GN OA dR TYPE nP ,
a 2 ACTUAT0R00MMMMMMMMSS T AA 1 S ,
E1 TT I S NES TYPE bb bbbb UCA GGNNNNGGGGRR
.I L VALVE NVC OR I EE ZSD NO IC SI ZE 2211 1 1 1 1 11 22 E VALVE M
S A
Y R
EO VG C XX LE AT VA C 8 AXXXXXXXXXX 7 L0 CATI 0N661 3571 35739 L 1 - - - - - - - - - - - -
O 5 DRAWI NG AAFFFFFF FFAB R -
T M U1 N /
O 2 C CLASS .
~
, 222222222222 E 4 C0DE M 5 U -
L M ABCDABC0 O / 239999222271 V 1 5566667 7 771 2 1 1 333333331 1 888888888888
- NUMBER CCCCCCCCCCCC m -
VVVVVVVVVVVV e . - - . -
t g VALVE VV s w 00 y r AA S D
, l .
D A M
E ttt sss R
yyy ll l 2 eell l vvaaa iiiii ssttt n ssrrr e aaaaa i PPPPP s
i 00 0 v L0 CATI 0N665591 1 881 99965999768 e -
R DRAWI NG CCEFCAACCCFFFEFFFDAAB .
U2 1 1 0 22 2, P, P REQUEST 222 22333 , -
RELIEF - - - - RRR - - RRRRR -- -- -
VVV VVVVV RR VV TIME 000000000 - - - - -- --- -- -- -- -- - - -- - - -
S TSTROKE 1 1 1 1 1 1 1 1 1 E S V EMAXIMUM QQ L T B, B, CC A JJJ RRR 222 B, B, V
M3 TEST
~
Q EEEE Q Q Q L, L, L,EERR/// QQJJRRRI QQI I I I EE A l QQ LLQQQ RD CEE EEE 2GN E OA .
dR TYPE -
nP ,
a 2 ACTUAT0R0000000 OOMMSSSSSSSSSS T MMMMMMMMM 1 S , -
- E1 TT I S NES TYPE G bb UCA GGGGDGGGGGGCCCRCCRRRR I L VALVE .
NVC OR .
I EE ZSD NO 4 4 I C SI ZE 44884332222448/44/232' 3 3 E VALVE M -
S A
Y R
EO VG C XXXXXXXXXX LE AT VA C BXXXX XX A XXX XX 6677222441 1 2266333564 8 L0 CATI 0N0DFF,CAA0DDEFGFFEFEAAB L 1 O 5 DRAWI NG R -
T M U1 N /
O 2 222222222222222222222 C CLASS ABA
. A8AB E 5 C00E BCDE05601 001 1 64228903 M 5 22220001 1 88884 2441 1 22 U - l 1 1 1 1 1 1 1 1 4 4 4 451 551 1 1 1 L M l 1 1 1 888888888888888B8 O / CCCCCCCCCCCCCCCCCCCCC V 1 VVVVVVVVVVVVVVVVVVVVV VVVVVVVVV
- # NUMBER CCCCOOOOO m LLLLMMMMM e . - - - -
t g VALVE VVVV s w OOOO y r MMMM S D l
D M tt E SS R
ll aa 3 ii tt VV rrVVVV I I aaII I I n PP PPPPPP e
i s
i 000 v L0 CATI 0N44328111 66887799994977 2 - - - - - - - - - - - - - - - - - - - - - -
R DRAWI NG BDBBFBCCBDFFFFFAA0AEAC U2 4
1 775555 REQUEST 553 1 1 - - - -
- - - - - - - - - - RRRR - - - - - - - -
RELI EF - - PPP - - - PPVVVV - - - - - - - -
TI ME 00000000 - - - - - - 5000 - - 22 332221 1 1 - - - - - - 1 1 55 - - 1 1 S TSTROKE 1 1 1 1 1 -
E S V EMAXI MUM L T A CCRRRR V
TEST RR CQQQQQ QQL,L,EEEEEE2222EEEE / / L L, L, L, Q Q Q Q I
, I QQ M3 EE EE A CC RRRR RD EE EEEE 2GN OA dR TYPE nP , -
a 2 ACTUAT0R0O000000 SSSSSS0O00SS0O T MMMMMMMM MMMM MM 1 S ,
E1 TT I S -
NES TYPE UCA GGGGGGGGCCCCCCGGGGRRDD I L VALVE NVC OR I EE ZSD NO 4 I C SI ZE 44442888008B8828883/33 1 1 1 11 1 1 1 3 E VALVE M
S A
Y R
EO VG C XXXXXX XX LE AT VA C BXX XXXX XXXX XX L
A A XX XXXX V
O M
E '
0 R 0 L0 CATI 0N7791 422266445533228355 2 - - - - - - - - - - - - - - - - - - - - - -
T 5 DRAWI NG BDBBFBCCBDFFFFF BBEAF AC A -
E M U1 H /
2 L CLASS A . 221 1 2222221 1 1 1 1 2222222 U 2 C0DE D 6 I - 01 S M A8 ABCABA8A8 A 1 1 E / 001 2366600669904 908966 R 1 000001 1 1 33334 4004500VV 7 7 7 7 1 7 7 777 7 79908007 7 CC 88888888888888980088FF
- # NUMBER HHHHHHHHHHHHHHHI SSHHHH m RRRRRRRRRRRRRRRSCCRRRR e . - - - - - - - - - - - - - -
t g VALVE VVVVVVVV VVVV VV s w OOOOOOOO OOOO OO y r MMMMMMMM MMMM MM S D
D A M
_ E eeeee R
_ vvvvv iiiii l sssss sssss aaaaa PPPPP n '
e i
s i 96797 v L0 CATI 0N - - - - -
a BFEBE R DRAWING U2 22222 REQUEST - - - - -
RRRRR RELI EF VVVVV TI ME - - - - -
S TSTROKE E S -
V EMAXI MUM L T A
V .
JJJJJ TEST RRRRR M3 LLLLL A
RD 2GN OA dR TYPE nP ,
a 2 ACTUAT0RMMMMM T
1 S ,
E1 TT I S NES UCA T' YPE D0D0D I L VALVE NVC -
OR IEE ZSD NO -
IC SIZE 23323 E VALVE M -
S A
Y R
N I
L L0 CATI 0N36637 O - - - - -
O DRAWI NG BFFBE C .
U1 L
E -
U CLASS F 33333 C0DE T
N 3 E 6 P -
S M 01 772
- # NUMBER 1 1 681 m 00770 e .
00880 t g VALVE F FFFF s
y ur SSSSS O O S D i
_ D A
_ M E
_ R 2
VV I I PP n
e i
s i 00000000 9976643333337799557 v L0 CATI 0N1 1 1 1 1 1 1 1 3 - - - - - - - - - - - - - - - - - - - - - - - - - - -
R DRAWING AABCAABCABECCFE0DBCCAAEDEFB U2 4 4
1, 1, 66 1 6 6 66 - - . 2 REQUEST 7777
- - - - - - - - - - - - - - - - - - - - - - RR - - -
RELI EF RRRR - - - - - - P - - - P - - PP - - - VV - - VR VVVV 1 I ME - - - - 000000300003300000 - - - - --
- - - - 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 - - - -
S TSTROKE E S V EMAXI MUM RR L T A L. L, V 2222 TEST RRRRQQQQQQCQQQCQQCCQQQ22QQR EEEEEEEEEEEEEEEEEEEEEERREEB M3 EE A
RD 2GN OA dR T YPE nP ,
a T
2 ACTUAT0RSSSS0OO000000O00000000SSSSS MMMMMMMMMMMMMMMAAA 1 S ,
E1 i T I S bbbbb NES 1 YPE bbbb UCA CCCCGGGGGGGGGGGGGGGGGGCCCCC I L VALVE NVC OR I EE ZSD 22222222 NO ////////
IC SI Z. E 1 1 111 1 1 1 444448844221 1 1 44441 / /
33 E VALVE 1 1 1 1 1 1 1 1 M
S A
Y R
EO XXXxX VG CXXXX LE AT VA C B XXXXXXXXXXXXXXXXXX A XX N
O 1 L0 CATI 0N1 1 1 1 22223346678779955533555 2 - - - - - - - - - - - - - - - - - - - - - - - - - - -
I T 5 DRAWI NG ABBCABBCABECCFEE0BCAABE0EFB C -
E M U1 J /
N 2 I CLASS 1 222
. 1 1 1 1 2222222222222AA2221 NN Y 4 C0DE T 6 E -
ABB AB AB A8A8 F M A8CDABCDAB 1 233467 7 3400355992 A / 000000001 1 77 8001 1 1 S 1 000000000000000001 99998 8888888888888888899999 8888B8BB88B8BB8B88888888888 1 I II I 1 I I I I I 1 I I I I 1 I I 1 I 1 I 1 I 1 1
- # NUMBER m SSSSS5SSSSS5SSSS5SSSS5SSSSS e .
VVVVVVVVVVVVVVVVVV t g VALVE s u OOOOOOOOOOOOOOO0D0 y r MMMMMMMMMMMMMMMAAA S D
D A o M r E t R S l
2 i
a tVVVV VVVV r1 I I I I II I n aPPPP PPPP c P ,
i -
s
-- 7'66771 0000 .
i v L0 CATI 0N664439J! 1 1 1 9E6466 R DRAWI NG DEEEEFFEFEE0 FEE 0DBAE0DE ~
U2 .
m REQUEST 66 86666 66667 . j RELI EF RR - - RRRRR - - - - RRRRR - - - - -
VV VVVVV VVVVV TI ME - - - - - 3300 - - - - -- -- -- -- -- -- -- - -
- - 1 1 - - - - - 1 1 1 1 S TSTROKE -,
E S V EMAXI MUM -
RRRR L T 2RRRR '
A V 22 R
/ L, L, , L L, m L, L L, L,2 TEST RRQQQ2222QQQQ2222RI 1 1 1 t M3 EEEEERRRREEEERRRRE /
A EEEE E EEE '
- 2GN RD OA dR nP ,
TYPE - _.' '
a 2 ACTUAL 0RSSD0SSSS5O0005 MM S5SSSS5SS MMMM . '
T 1 S ,
E1 T T I S -
NES TYPE UCA CCGGCCCCCGGGGErCCCRRRRR I L VALVE NVC ,
OR -
I EE ZSD NO 44444 I C SI ZE / / / / /
44668882244442222333333 E VALVE M -
S A _
Y R
EO VG CXx XXXXX XXXXXXXXXX LE AT VA C B XX XXXX A
XXXX XXXX ,
N O 1 L0 CATI 0N55777- 223344 441 1 1 - 1 -245744 I
T C
2 5
DRAWI NG EFEEEF FFVEEEFFFEEBAEDEF E M U1 J /
N 2 I CLASS
. 222221 1 1 1 22?21 1_i 1 222222 Y 4 C0DE _
T 6 -
E - '
F M ABAB CDC0ABaBA8CD A / 22336994 4 00l l 2222223801 S 1 222224 4 001 1 l l 1 1 1 1 355533 99999 990000000000088800 8888HB89999999999988899
- # NUMBER 1 1 1 1 I I 1 1 1 1 I 1 1 I I I I I 1 1 1 I 1 m 5555SSSSSSS55SSSSSSSSSS e .
VVVV t g VALVE VV s u OO eOOOO y r MM NMMM S D ~ j '
R l 8 el eeee l 1 exo vvvv ASb2 c iiii ss ss V 2 ssss . I aaaa V?VVVVVV F PPPP I l I I I II I PPPPPPPP n
e i 0000 6 i
s L0 CATI ON965899884331 1 1 1 BBBB0EFFEEACCCCBBBBDEE0 965B9941 v DRAWING R U2 7
44 2 3 -
- 1,1,1 99999999665R REQUEST 99 - - - - - - - - - 1 1 -
V.
- - - - - - - - - - RRRRRRRRR - - R RELI EF - - - - - - - - PPVVVVVVVVVPPV0 1 P
TI ME - - - - 2 200550 - - ' - - - - - - - - -
- - - - 1 1 44 1 1 6 - - - - - - - - - - - -
S TSTROKE E S V EMAXI MUM L T RRRRRRRR A J L,L L,L,L,L L,L V
R M3 TEST - - - - Q Q Q Q C C
- - - - EEEEEE
't, R22p2p222 RRRRRRRCCR ?
L, .
A Q////////EEEC RD ECCCCCCCC E 2GN EEEEEEEE OA dR TYPE nP ,
a 2 ACTUAT0ROOOO0DO0DO0 T MMMMMMMMMMAS5SSSSSSSSSS 1 S ,
E1 TT I S NES TYPE -
b UCA GGGGGGGGGGGCCCCCCCCClCC I L VALVE '
NVC OR I EE ZSD NO I C SI ZE 00000088221 0000000000E3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 E VALVE M
S A
Y R
EO VG C XXXXXXXXXXXX LE AT VA C BXXXXXXXXXX 3~
A xXXXXXXX?, X N
O 2 L0 CATI 0N26743333899222226742281 I 2 T 5 DRAWI NG BBBBDEF FDDACCCLBB0SDEED C -
E M U1 J /
N 2 I CLASS
, 2222222222A1 1 1 1 1 i i 1 2221 Y 5 C0DE N T 6 E -
A F M ABCDABABA8 ABCDABCDAB 7 81 A
S
/
1 8888991 1 0000001 1 2208088%6667 1 1 8444 4 5555550 88888888888 999939999990 888B88BB888aBB888888889 1 I I I 1 1 I I 1 1 1 l I I 1 I 1 I I ; 1 1 1
- NUMBER m 5SSS55SS55SSSS5S5SSS55S e . - - - - - - - - - - -
t g VALVE VVVVVVVVVVV s u OOOOOOOOOO0 S
y D
r MMMM.MMMMMMA i .
- t & ,; i - # - = -
-7 3 9~~,~ .
3 R7 t'
0 -
3 y /
0 1
S y
t e K -
a R D A M
E R
2 VVVVVVV 1IIIIII
._ n - PPPPPPP o
i 2 s
i 000D000 v
e LOCATION 1 11I 111 9668993
- - - - - - - - - - - - - - = _
R _ O E' AWING DEEDDEEAAAADDA
~ U2 -
7777777 2222222 3
- - - - - - - 1 REQUEST RRRRRRR -
V,V,V,V,V,V,V,-- - - - - - R RELIEF - - - - - V 8808888 1 1 1 1 1 1 1 PPPPPPP
- TIME - - - - - - -
S T STROKE - - - - - - -
- f. S V E MAXIMUM L T J A .
R V RRRRRRR,1 L, M3 TEST L,L,L,L L L,1, I I LII
~
lA I- GN RD CCCCCCC EEEEEEE I
' GA 2 TYPE 0 dD, n 2 a 2 ACTUAT6R ~
SSSSSSSSSSSSSS -
T 1 S ,
L1 T1 I S NES TYPE UCA CCCCCCCRRRRRRR I L VALVE NVC OR IEE D
ZGO iC SI IE 88888881 11 1 221
-- E V'ALVE
- M S
A Y
R EO VG C XXXXXXXXXXXXXX LE AT
- VA
- C B c-A XXEXAXX X N
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I n
4.3.1 IWV - Positions In this section it is the station's intent to specify with respect to ASME Section XI applicability, interpretation, and specifics relevant to this station. It is not the station's purpose or intent to minimize the requirements but to meet the code intent to the fullest. .This at times requires a clarification due to vagueness in certain areas and specifics, when examinations are required on components with built in construction restrictions.
The following Positions' apply strictly to the station and are intended to clarify . interpretation of the code for both'the station and authorities.
Zion's Positions are general and specific. Where a strict reading of the ASME requirements yields insufficient guidance to implement the' Code'at Zion Station,'the Zion's stated Positions will be utilized as clarification and will define the Station'sl interpretation of ~the Code.
These Positions alsoLidentify why the valves are stroke exercised during all cold shutdowns and not stroke exercised quarterly per the A5ME code.
212a 1019t 0459A
i
=
Valve Position il The ASME code, IWV-3415, requires that valves with fail safe actuators be observed quarterly during loss of actuator power. This will be accomplished at Zion Station by observing that the indicator lights in the control-room show the correct position as valve is stroked, if relief is being requested f rom' stroking a valve with f ail safe actuator, it should be assumed that relief is also being requested from testing the fail safe actuator. !
i c
Valve Position #2 It is the station's position that HOV-M50001, 2,'3 and 4 main steam isolation valves will not be full stroke exercised during power operation because closure would result in a reactor trip and safety injection. These 3 valves are partially stroke exercised at least quarterly and full stroke j' exercised during cold shutdowris.
Valve Position #3 It is the station's position that valve MOV-RH8703 will not be full stroke exercised during power operation. Failure of MOV-RH8703 in the closed position would render the Residual Heat Removal System to the hot legs inoperable. The valve will be full stroke exercised during cold shutdown.
212b 10191 0459A
)
1 Valve Position #4 It is the station's position that valves PCV-4550 and PCV-456 (power operated relief valves) will not be full stroke exercised during power operation. Exercising these valves could potentially lead to depressurization of the reactor coolant system if the PORV block valves RC8000A, B leaked through. Valves PCV-455C and PCV-456 will be full stroke exercised during cold shutdown.
Valve Position-#5 It is the station's position that MOV-RH8701 and MOV-RH8702 (residual heat removal loop suction valves) will not be full stroke exercised during power operation. These valves are not designed to open under normal operating differential pressures and attempts to open these valves that are interlocked to reactor coolant pressure could overpressurize the residual heat removal lines. These valves will be full stroke exercised during cold shutdowns.
Valve Position #6 It is the station's position that MOV-SIB 802, MOV-518806, MOV-518813 and MOV-518814 valves will not be full stroke exercised during power operation.
Failure of any of these valves during unit operation would render the Safety injection System inoperable. These 4 valves will be full stroke exercised during cold shutdown.
212c 1019t 0459A
. . I Valve Position #7 It'is the station's position that valves A0V/M0V-M50017, 18, 19 and 20 (atmospheric relief' valves) will not be full stroke exercised during power operation because it could potentially cause a power surge and possibly a reactor trip. These valves will be' full stroke exercised opened and then closed during cold shutdown.
Valve Position #8 it is the station's position that valves MOV-FWO0l6,17,18 and 19 will not be' full stroke exercised during power operation because closure would result in a loss of steam generator level control and a reactor trip. These valves will be full stroke exercised during cold shutdown.
Valve Position #9 It is the station's position that f ailure of MOV-518812A and B in the closed position during quarterly full stroke exercising could render the Residual Heat Removal System inoperable. Therefore these valves will be full stroke exercised during cold shutdown.
4 l
I 1
l 212d 1019t 0459A I
... .' 1, Valve Position #10 Withdrawn ,
Valve Position ill i It'is the Station's. position that check valves M50008, 9, 10 and 11 cannot
~
be backflow tested during power operation because this would require cycling the reactor to hot standby to perform the test. These valves will be backflow tested when coming out of cold shutdown and will not be tested in excess of f
the quarterly requirement.
Valve Position #12 Withdrawn Valve Position #13 It is the station's position that valves such as containment isolation valves and the pressurizer block valves to the power operated relief valves need not follow the exercising f requency when closed for isolation purposes.
If a test frequency-is missed, the valve will be stroked prior to returning it to service. If a valve remains closed throughout the operating cycle, it will be stroked during the cold shutdown.
I 212e
- 10191
-0459A 4
Valve Position #14 Zion Station has identified a section of the Zion Technical Specifications which may be interpreted as conflicting requirements. This valve position will clarify the station's position on section 4.4 of the Technical Specifications. Valves in section 4.4 which are indicated to be stroked at ref ueling outages may also be stroked to f acilitate other plant testing, during plant evolutions or in cold shutdown. This Technical Specification references valves MOV-518802, MOV-518806, MOV-518812A and B, and MOV-RH8703.
These valves will be stroked at cold shutdown and refueling outages in accordance with the 151 Program. (See Valve Positions #3, #6 and #9.)
Valve Position #15 It is the station's position that Aux. Feedwater Suction Valves MOV-FWOO74, MOV-FWOO75 and MOV-FWOO76 will not be f ull stroke exercised during power operation. Failure of these valves in the closed position during unit operation would isolate the water supply to the aux. feedwater pumps and this could potentially damage the pumps if actuated. These valves will be full stroke exercised during cold shutdown.
Valve Position #16 It is the station's position that the check valves to the cold legs, SI8957a and B will not be exercised during power operation. These valves will be f ull stroke exercised at cold shutdown when the RC5 pressure is low enough to reach the flow conditions necessary to ve ify full disk lift.
Valve Position #17 t' It is the station's position that check valves RH8730A and B cannot be full stroke exercised durir.g unit operation as the shut of f head of the pumps is lower than reactor coolant system pressure. Partial stroke exercising of these check valves will be demonstrated by establishing proper RHR pump discharge flow in the recirculation line during periodic pump testing at least quarterly.
Full stroke exercising of these check valves will be demonstrated while the RHR system is in normal operation for the reactor coolant system during cold shutdown. This condition is required to provide system flow conditions similar to design injection flow. This alternative will assure the required l level of safety and that operational readiness is maintained.
212f I
1019t 0459A
l i Valve Position #18 o It is the Station's position that check valves for the Safety Injection Cold Legs S19001 A thru D and 519002A thru D shall be full stroke exercised at cold shutdown. At cold shutdown, the RCS pressure is low enough to inject ,
adequate flow through the check valves to achieve full stroking.
' Valve Position #19 It is the Station's position that FCV-1A01 A and B shall be stroked at cold shutdown. Failure of FCV-1A01A and B in the closed position during power operation would cause the unit to lose letdown and thus lose pressurizer level control. Also instrument air to containment would be shut of f. This is considered poor engineering judgement to risk stroking these valves at power operation.
Valve Position #20 It is the Station's position that valves CC9463A,B.and OCC9464 be tested for reverse flow quartcrly except where plant conditions do not permit doing so. For example, if one of the component cooling pumps is out of service, i
plant conditions may be such that the other 4 pumps must be in operation to provide adequate cooling throughout the piant. Therefore, shutting off one of the pumps to test for reversed flow through a discharge check valve could place the plant in an unsafe mode of operation. If reverse flow cannot be performed during the quarterly testing it shall be performed during the next quarterly scheduled test. If the station is in a cold shutdown and the interval between the tests is greater than 3 months, then the valves shall be tested during the cold shutdown.
Valve Position #21 It is the Station's position that valves VC8542A, B which are the charging pump mini-flow check valves be tested for reverse flow each cold shutdown. In order to perform a reverse flow test for these valves it will be necessary to isolate one of the pumps at a time from its suction. During power operation, this would be considered poor engineering practice and would place the plant in a less conservative mode of operation. Therefore the valves shall be tested for reverse flow each cold shutdown.
I 2129 l 1
1019t
- . 0459A
i 4.3.2 IWV - Reliefs 213 1
1019t 0459A i
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l Valve Relief fl 1
Relief is requested from the exercising requirement of Section XI for spray j additive check valves 05-0016, C5-0021, and C5-0026. l Code Requirement I
IWV-3522 (full stroke exercise quarterly) i Basis and Alternate Full stroke exercising of check valves in the spray additive system will add sodium hydroxide into the spray system and cause spraydown of the containment building. To disassemble and remove each valve requires breaking the valve bonnet, with this consideration, one valve will be disassembled and inspected each refueling outage. Results of the inspection will be reviewed and if the valve f ails the other two will be inspected. This alternative will provide adequate assurance that operational readiness and safety will be maintained.
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10191 0459A
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Valve Relief #2 -
Relief is requested from performing seat leakage testing required by IWV-3420 thru IWV-3427 on'the attached valve list. ll I
Code Requirement IWV-3420 thru IWV-3427 (Leak Testing Requirements).
ll Basis and Alternate The attached list of valves function as containment isolation valves and are supplied by an Isolation Valve Seal Water system which is functionally tested as' part of this program and Technical Specification 4.9.1.
These valves are tested.in accordance with 10CFR50 Appendix J as required by Technical Specification 4.10.
- These valves are tested in large groups. Leakage from these valves is not calculated; the test is satisfactory if the pressure in the IVSW headers is maintained in accordance with Technical Specification'4.10. Therefore trending of seat leakage cannot be performed.
This alternative will provide adequate assurance that safety and operational readiness will be maintained.
215
\1019t 0459A
Valve List Relief #2 .
The following valves are applicable to Relief Request VR-2 A0V RV0005 RC8025 FCV PR19A A0V RV0006 RC8026 FCV PR19B FCV RV111 RC8028 FCV PR20A FCV RV112 RC8029 FCV PR20B FCV RV113 SF0010 FCV PR21A FCV RV114 SF8767 FCV PR21B MOV CC9414 SF8787 FCV PR22A MOV CC9438 05F0011 FCV PR22B MOV CC685 05F0012 FCV PR23A MOV VC8100 559354A FCV PR23b y MOV VC8105 559354B HOV CC9413A MOV VC8106 559355A- MOV CC9413B VC8480A 559355B VC8480B 559356A A0V VC8152 559356B A0V VC8153 559357A VC8369A- 559357B-VC8369B DT9159A VC8369C- D19159B VC83690 DT9160A
'VC8372A 0T9160B VC8372B DT9170 VC8372C DT LCV1003 VC83720 DWOO30 DWOO38 FCV WD17A FCV WD17B FCV VF01A FCV VF01B FCV VN02A FCV VN02B FCV SA01A FCV 5A01B 216 1019t 0459A
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-Valve Relief f3 - .~
Relief is requested f rom full stroke testing of charging pump suction, and discharge check valves due to system configurations and parameters. Valves VC8481A, B, and VC8546.
Code Requirement IWV-3521 (exercising frequency) ,.
1WV-3522 (exercising procedure) ,i A
, Basis and Alternate Full stroke exercising of the. charging pump suction check valve cannot be 5))
demonstrated during unit operation as the reactor coolant system precsere< >
prevents the pumps f rom reaching f ull injection flow conditions. , <
Additionally, suction would have to be switched f rom the VCT to the RWST.
This would inject 2000 ppm borated water into the Reactor Coolant System and would set up a power transient that would cause a xenon oscillation which is not desirable.
Performance of this test with the recctor coolant system intact could lead to an inadvertent overpressurization of the system. The alternative method of !
protecting against overpressurization by partial draining of the reacter coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor 1 core.
Full stroke exercising of these check valves will be demonstrated during refueling while the reactor vessel head is removed. This alternative will assure the required level of safety and that operational readiness is maintained.
1hese valves can be partially stroked quarterly. Valve VC8546.will be exempt f rom partial stroking when the unit is at end of core life since this would also setup a power transient that would cause a xenon oscillation during this period. This period typically occurs during the last quarter of core life.
i 221 1019t 0459A r
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Vaive Relief #4 Withdrawn (Reference Valve Position #17) l l
22, i
1013t 0459A i
.___.______--____-___---_..____-______D
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Valve Relief #5 l
' Relief is requested f rom full and partial stroke exercising due to system configurations and parameters. These valves are RH8736A, RH8736B, RH8949A, '
RH8949B and 518958.
h Code Requirement i I
IWV-3521 (test frequency)
IWV-3522.(exercise procedure) '
L 8 asis and Alternate ,
These check valves cannot be exercised during unit operation as the shutof f head of the pumps is lower than reactor coolant system pressure.
Full stroke-exercising of all the branch run check valves with the reactor
- coolant system depressurized but intact would not provide adequate surge volume for influx f rom the RWST to allow the RHR injection system to reach design flow. The alternative method of providing a surge volume by partial draining of the reactor coolant system is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core. This testing also requires that all RHR is injected through the hot legs only, thereby isolating cooling flow through the reactor core.
Full stroke exercising of all the branch run check valves will be demonstrated
- by total pump discharge flow during refueling while the reactor vessel head is removed. This condition is required to establish suction from the RWST and provide system flow conditions similar to design flow.
The flow.through each hot leg injection line shall be verified by temporarily installed dif ferential pressure gages and calculating the flow f rom the differential pressure.
This. alternative will provide adequate assurance of the required level of safety and that operational readiness is maintained during this interval.
223 10191 0459A 4
-__mm.__._ ___. _ . _ . _ _ _ _ _ _ _ _ . _ _ _ _ . - _ . _ _ . - . _ _ . _
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1 l 1 Valve Relief f6 Relief is requested from full and partial stroke exercising due to system
! configurations and parameters on valves SI8905A, 518905B, SI8922A, 518922B, 5189490, SI8949D, 5190040, 519004D, SI9012A, 519012B, 5190120, 5190120. ,
i I
Code Requirement IWV-3521 (test frequency)
! 'IWV-3522 (exercise procedure) {
Basis and Alternate These check valves cannot be exercised during unit operation as the shutof f.
head of the pumps is lower than reactor coolant system pressure. Full stroke exercising of all the branch run check valves with-the reactor coolant system depressurized but intact could lead to an inadvertent overpressurization of the. system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
Full stroke exercising of all the branch run check valves will be demonstrated by total pump discharge flow during refueling while the reactor vessel head is removed. This alternative will provide adequate assurance of the required level of safety and that operational readiness is maintained during this interval.
224 1019t 0459A I
Valve Relief #7 Relief is requested f rom full and partial stroke exercising due to system configurations and parameters on valves 518900A, 518900B, 5189000, 518900D and 519032.
Code Requirement t;
IWV-3521 (test frequency)
IWV-3522 (exercising procedure)
Basis and Alternate These check valves cannot be full stroke or partial stroke exercised during unit operation as the injection of cold, highly borated water would result in a change in reactor core recctivity, a large xenon oscillation, and undue thermal cycling of the injection nozzles.
Full stroke exercising of all the branch run check valves with the reactor coolant system intact could lead to an inadvertent overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
These check valves cannot be partial stroke exercised during cold shutdown with the reactor vessel head intact because that could result in a low temperature overpressurization condition.
Full stroke exercising of all the branch run check valves will be demonstrated by totai pump discharge flow during refueling while the reactor vessel head is removed. This alternative will provide adequate assurance cf the required level of safety and that operational readiness is maintained during this interval. ,
225 1019t 0459A
- _ . ___________a
Valve Relief f8 Relief is requested from full stroke exercising due to system configurations and parameters for valve 51-8926.
Code Requirement IWV-3521 (test frequency)
IWV-3522 (exercise procedure)
Basis and AIternate This. check valve cannot be full stroke exercised during unit operation as the j' shutoff head of the pumps is lower than reactor coolant system pressure.
~
Partial stroke exercising of this check valve will be demonstrated by establishing proper pump discharge flow during periodic pump testing.
Full stroke exercising of this check valve with the reactor coolant system )
intact could lead to an inadvertent overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level-above the reactor core'.
Full stroke exercising of this check valve will be demonstrated during refueling while the reactor vessel head is removed. This alternative will provide adequate assurance of continued operational readiness and maintain the required level of safety.
I i
1 226 1019t 0459A
. 4
,, .. 4 Valve Relief #9 Relief is requested from full and partial stroke exercising due to system configurations and parameters on valves 1
SI8948A, 518948B, 5189480, 518948D 1 l
SI8956A, 518956B, 5189560, and 5189560 1
Code Requirement ;
IWV-3521 (test frequency)
IWV-3522 (exercise procedure)
Basis and Alternate The accumulator check valves cannot be exercised during unit operation due to the pressure differential between the accumulators (600 psig) and the reactor '
coolant system (2235 psig). Full stroke exercising of these valves can be done by dumping one accumulator under nitrogen pressure into a partially drained refueling water cavity during refueling with the reactor vessel head off.
i Zion Station is proposing to test one set of two accumulator valves per refueling outage using this method since this test involves considerable time I
and expense with arguable benefit. The initial conditions of the test are l extensive. Temporary instrumentation must be installed and accumulator tank I samples are obtained to verify fluorine, chlorine, sodium and boron concentrations are within applicable limits. If water chemistry is not within the specifications, then the accumulator must be drained, filled, and resampled until satisf actory results are obtained.
Due to the required plant conditions to perform the testing (reactor head off, lower reactor internals installed and specified reactor cavity level), this must be per formed on critical path time. Thus, additional accumulator testing would directly affect the total outage length.
This test also has the unavoidable potential to introduce a crud burst into the reactor coolant system. Testing more than one accumulator per outage will increase the potential crud burst. Crud in the RCS can result in higher dose rates and, instrumentation and fuel fouling.
i We believe that the costs of testing all accumulators every outage in terms of set up time, critical path time, and the potential for crud bursts more than outweigh the actual benefits. Previous test results suggest Zion Station does l not have problems with full disc lif t of the accumulator check valves. The proposed test schedule will verify this fact in a timely manner.
In addition these valves will be partial stroke exercised during cold shutdown. This alternative will provide adequate assurance of continued operational readiness and maintain the required level of safety.
i 227 1019t 0459A
Valve Relief #10 W11HDRAWN 4
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i l!
l 226 1019t 0459A i
i 1
l I
l q
Valve Relief #11 l Relief is requested from stroking requirements due to system operational l requirements on valves:
I MOV-CC9413A, H0V-CC9413B, MOV-CC9414 MOV-CC9438 and MOV-CC685.
Code Requirement IWV-3411 (test frequency)
IWV-3412 (exercising procedure)
Basis and Alternate.
Component cooling water flow to the reactor coolant pumps is required at all times the pumps are in operation. Failure of one of these valves in a closed position during an exercise test would result in a loss of the cooling flow to the pumps.
The valves will be exercise tested during cold shutdown providing all reactor coolant pumps are not in operation. This testing period will be each ref ueling outage as a maximum. This alternative will provide adequate assurance of continued operational readiness and maintain the required level of safety.
229 1019t 0459A
Valve Relief f12 Relief is requested f rom stroking requirements for Isolation Valve Seal Water
. check valves. (See attached list)
Code Requirement IWV-3521 (test frequency)
IWV-3522 (exercising procedure)
~ Basis and Alternate These IV5W check valves can only be tested by observing flow through downstream tell-tale drain or by disassembly of the valve to verify proper disk freedom of movement. .This testing would render the system unable to perform its safety function and it would extend each cold shutdown 36 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. It would also require an additional 0.5 man rem each test. To perform
- the test, the reactor coolant pumps would have to be shutdown and it would require draining the' isolation valve seal water system along with portions of the volume' control system. The isolation valve seal water may not contain
. primary grade water therefore post test flushing would be required causing additional loading on the radwaste system. Increased testing frequency is not necessary as the IV5W system has had very good performance to date.
These valves will be tested at a refueling outage frequency. This alternative will provide adequate assurance of continued operational readiness and maintain the required level of saf ety.
230 1019t 0459A s
\
Valve list Relief #12 The following valves are applicable to Relief Request VR-12 IW0001 IWOO58 IWOO80 IWOO59 IWOO81 IW0003 IWOO73 IWOO60 IW0082 IWOO74 IWOO61 IWOO83 IWOO75 IWOO62 IWOO84 IWOO76 IWOO63 IW0162 IWOO77 IWOO64 IWOO90 IWOO78 IWOO65 IWOO95 ,
IWOO79 IWOO66 IWO186 IWO181 IWOO67 IW0182 IWOO68 IWO183 IWOO69 IWO184 IWOO10 IW0185 IWOO72 IW0198 l
231 1019t 0459A
... e ., ,
r Valve Relief f13 Relief is requested from leak test requirements as required of IWV-3420 thru ,
IWV-3425 of ASME Section XI Code for the valves on thu attached list. <
Code Requirement IWV-3420 thru IWV-3425 (Valve leak test requirements)
Basis and Alternate The attached list of containment isolation valves are required to be Type C leak tested per Technical Specification 4.9.3.
l .These valves are leak tested in accordance with 10CFR50, Appendix J. Any additional testing of these valves in accordance with ASME 5ection.X1 would not provide added assurance of valve readiness.
Valve 518857 is not in the Technical Specification as a containment isolation valve, however, it will be tested in accordance with 10CFR50, Appendix J.
This alternative will provide adequate assurance that safety and operational l readiness will be maintained.
i 232 1019t 0459A f
---___---.-.---._-__m_____2
n- -- - -
Type C Leak Tested Containment Isolation Valves A0V-DT9157 A0V-RV0003 FCV-IA01A A0V-RV0004 FCV-IA018 A0V-SI8880 FCV-PR24A CS-0005 FCV-PR24B CS-0009 SOV-PR25A CS-0013 SOV-PR25B CS-0037 50V-PR25C CS-0038 SOV-PR250 CS-0040 SOV-PR26A CS-0041 50V-PR26B CS-0043 50V-PR26C CS-0044 50V-PR26D OT-9158 A0V-RC8033 PR-0029 A0V-RV0001 PR-0030 A0V-RV0002 RC-8045 51-8857 232a 10571 0505A 1- ---- __ _____._
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i j
i 9
Valve Relief #14 Withdrawn (Reference Valve Relief #13) 1 233 j
1057t l 0505A !
\ _. __ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ -
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Valve Relief #15 WITHDRAWN 234 1057t 0505A l
- Valve Relief #16 Relief is requested f rom the exercising requirement of ASME Boiler and Pressure Vessel Code Section XI for Diesel Generator Starting Air Check Valves.
Code Requirement IWV-3522 (full stroke exercise quarterly)
Basis and Alternative Each diesel generator has two starting air compressor receiver check valves that go to a common header to start the engine. To test the diesel generator starting air compressor receiver check valves 10G0037, 38, 39, 40, ODG0025, 26 and 20G0033, 34, 35, 36, the associated diesel generator must be started once for each of the two valves in its system.
The Nuclear Regulatory Commission (reference Generic letter 84-15) and Zion Station are trying to eliminate unnecessary fast starts of the diesel generators to increase reliability of the engines. Generic letter 84-15 is ll attached.
Additionally the starting air system is configured in such a way that full stroking the check valves would require isolating one of the receivers at a time and starting the diesel. This would eliminate redundancy and place the plant-in a less conservative mode of operation. At least one check valve can be verified to partially stroke quarterly during diesel testing.
Also, one valve per diesel generator will be disassembled and inspected each 0 refueling outage (the other valve will be inspected in the next refueling outage).
234a
} I j 1057t l 0505A
,{ g-
.... JUL i4 E1 10 ALL' LICENSEES OF OPERATING REACTOR 5, APPLICANTS FOR AN OPERATING -
. LICENSE, AND HOLDERS OF CONSTRUCTIDH PERMITS
. Gentlemen: ,
SUSJECT: PROPOSED STAFF ACTIONS TO IMPROVE-AND PAINTAIN
- g. DIESEL GENERATOR RELIABILITY (Generic Letter 84-15)
As part of the proposed technical evaluation of Unresolved Safety Issue (USI) ;
A 44, Station Blackout, the staff is considering new requirements that would j reduce the risk of core damage from station blackout events. The reliability of diesel generators has'been identified as being one of. the main factors affecting the risk from station blackout. -Thus, attaining and maintaining high-reliability of diesel generators is a necessary , input to the resolution of USI.
A- 44 '.
Plants licensed since 1978 have been required to meet the reliability goals of Regulatory Guide 1.108.for their diesel generators. However, the staff has detemined that many. operating plants do not have reliability goals in place for their diesel generators. Considering the critical role diesel generato.rs play in mitigating various transients and postulated events following 'a loss
'of effsite power, the staff has determined that there is an important need to assure that the reliability of diesel generators at operating plants is
~
maintained at an acceptable level. The staff has deterTnined that the risk
. from station blackout is such that early actions to-improve diesel generator reliability would have a significarrt safety benefit. Toward this objective, p we.have developed the following approach to assess and enhance, where necessary 1 -
the reliability of diesel generators at all operating plants.
The items covered by this letter fall into the following three areas:
1; 1. Reduction in Number of Cold Fast Start Surveillance Tests for .
{. _ Diesel Generators 1 *-
This item is directed to' wards reducing the number of cold fast start surveillance tests for diesel aenerators which the staff has determined
]f results in premature diesel engine degradation. The details relating to this -subject are provided in Enclosure 1. Licensees are requested to describe their current programs to avoid cold fast start surveillance
~
3 testing or their intended actions to reduce cold fast start surveillance testing'for diesel generators.
f 2. _ Diesel Generator Reliability Data This item requests licensees to furnish the current reliability of each diesel generator at their plant (s), based on surveillance. test data.
j Licensees are requested to provide the infomation requested in Enclosure 2. -
.J 4
8407o2o205 234b' s .
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.. . ,, . i
- 3. Diesel Generator Reliability Licensees are requested to describe their program, if any, for attaining and maintaining a reliability goal for their diesel generators. An example ;
of a performance Technical Specification to support a desired diesel generator reliability goal has been provided by the staff in Enclosure 3. * !
Licensees are requested to comment on, and compare their existing program or anj proposed program with the example performance specification.
Accordingly, pursuant to 10 CFR 50.54(f), operating reactor licensees are requested to furnish, under oath or affirmation, no later than 90 days from the date of thi.s letter, the information requested in Items 1 through 3 above.
Applicants for operating licenses and holders of construction permits .are not required to respond.
Licensees nay request an extension of time for submittals of the required inf orma tion. Such a reouest must set forth a proposed schedule and justification for the delay. Such a request shall be directed to the Director, Division of Licensing, NRR. Any such request must be submitted no later than 45 days from the date of this letter.
t This request for information has been approved by the Office of Management and Sudget under Clearance Number 3150-0011, which expires April 30, 1985.
Sincerely, u
uarrei D e Division'ofks'enu icensing
Enclosures:
- 1. Reduction in Number of Cold Fast Starts for Diesel Generators '
- 2. Diesel Generator Reliability d Data
- 3. Diesel Generator Reliability .
e 234c .
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., . ., . j l
Va lve Relief #17_
Relief is requested from the increased frequency and corrective action for t motor and hydraulically operated valves that normally stroke in 5 seconds or less and for air operated valves. ,
I
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Code Requirement I IWV-3417(a) (increased testing frequency and corrective action)
I Basis and Alternate Relief is requested f rom the requirements of IWV-3417(a) for motor and i hydraulically operated valves that normally full stroke in 5 seconds or less with respect to increased testing frequency and corrective action based on a percent stroke time increase. Relief is also requested from these requirements for air operated valves.
For motor and hydraulically operated valves that normally full stroke in 5 seconds or less, the normal fluctuations in valve stroking times combined with operator reaction time errors can introduce erroneous readings up to 100% of the stroke time. This would cause unnecessary administrative work and increased testing. ,
As an alternative, f ast acting valves that normally stroke in 5 seconds or less will be tested more frequently when stroke time increases by 100%. For ;
valves that normally stroke in less than i second, the maximum stroke time for these valves will be 2 seconds and no trending of stroke times will be required.
Historical trend data collected since 1984 for both Unit 1 and 2, has typically shown a wide range of stroke times for air operated valves (see Attachment A). Variations in the supplied air pressure due to demand along with variations in the system pressure will cause fluctuations in the stroke times. Also how fast the operator reverses the position of the valve and The whether the pressure has stabilized or not will af fect the stroke times.
shorter the stroke time of the valve, the greater these items along with operator reaction time will contribute to the stroke time fluctuations. Zion Station proposes that the frequency of testing will be increased to monthly when the stroke time for air operated valves that normally stroke in 10 seconds or less increases 100% over the reference mean stroke time for the valve or that normally stroke in greater than 10 seconds increases 25% over the reference mean stroke time for the valve. The reference mean stroke time is the sum of the stroke times of several consecutive tests, divided by the number of tests. The mean may be re-established after maintenance has been performed on the valve which may alter the stroke time. The mean will be re-established only through an engineering evaluation.
These alternatives will provide adequate assurance of continued operational readiness and maintain the required level of safety.
234d 1057t 0505A
L y z.
n.
Valve Relief #18 DM 3-R'e' lief:isrequestedfromobservingvaIvesw" indicators once ,1 sp$y
. every two years. ty;@R n ug.
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Code Requirements .y;M
- f,
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IWV-3300 (valve position indicator verificat : i fg5
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Basis and Alternative _ A y%
m, Relief is requested.from observing valves w indicators once- IW St every two years. Historically . nuclear powi on a 1 year' J Jb;i
. refueling cycle. Therefore in each two yea- two refueling @i outages'per unit in which to perform the te n indicators. ; r$: W,1 $9""
in order to minimize personnel exposure in the work load ~
~
during a refueling outage. Zion Station pre- inspect all
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-remote position indicators for each unit ev outage. Zion b .[,E sO'"d-Station will be going to an 18 month refuei following its . 6% f 1985 refueling outage and for Unit 1 follow ng outage. .To j ' Mg , -
test all valves with remote position indica- ueling outage 1 ~4 in a two year period would mean coming down efueling [4$," _
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outage, and would increase personnel exposur' ,
Zion Station proposes to test all valves fc .ote position 4p(g n. ~pi , ' .
indicators every other refueling outages or three years. i , - -
This alternative will assure the required I hat operational Di%
readiness is maintained. fW.. i; .
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e Valve' Relief #19 Relief is requested from the exercising requirement of Section XI for Reactor Vessel Head Vent Valve 50V-RC08, 9, 10 and 11.
Code Requirement IWV 3522 (exercising frequency) .
. Basis and Alternative The Reactor Vessel Head Vent Valves 50V-RC08, 9, 10 and 11 cannot be exercised during power operation. The normal position of these valves is deenergized shut. Failure of these valves in the open position during testing could result in.a small break loss'of coolant accident.
These valves will be full stroke exercised during cold shutdown and refueling outages when all reactor coolant pumps are secured and the reactor coolant system is depressurized.
1 1
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- c. . e Valve Relief #20 Relief is requested from full stroke exercising valve MOV-VC8100 during power ,.
operation.
U f
Code Requirement
.IWV-3412(a)'(exercising procedure) q Basis and Alternate q r
Stroking valve MOV-VC8100 during power operation could potentially damage the reactor coolant pump seals. Therefore MOV-VC8100 will be full stroke exercised during cold shutdown when all reactor coolant pumps are secured.
2349 1057t 0505A
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Valve Relief #21 Relief is requested from back flow testing check valve S18912 for the Boric Acid Injection Tank Recirculation Line at a quarterly test f requency.
Code Requirement l IWV-3521 (Test Frequency)
Basis and Alternative Relief is requested f rom back f low testing valve S18912. The boric acid system is required to be in constant operation providing reactivity control to the reactor coolant system therefore it cannot be tested during operation.
This valve will be tested during refueling outages. This testing can only be perfonned at refueling outages because the testing requires closure of VC8446B which isolates blending flow capability. This system is necessary to maintain the boron concentration in the RCS during both power operation and cold shutdown conditions. Other emergency boron addition techniques would tend to over borate the RCS and would necessitate dilution. If this were to occur during a cold shutdown, it may significantly impact the length of an outage until RCS water chemistry was back within Tech Spec limits. Therefore valve 518912 shall be tested each refueling outage.
Additionally a proposal is being drafted to permanently remove the Boric Acid Injection Tank Recirculation Line f rom service. If this proposal is accepted, check valve S18912 will be exempt f rom test requirements and will be removed from the IST program.
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Valve Relief #22 Withdrawn 234i
~1057t 0505A
e Valve Relief #23 kelief is requested f rom IWV-3522 for charging mini-flow check valves VC8542A and B.
Code Requirement IWV-3522 (Exercising Procedure) ,
i!
Basis and Alternative
' Lion Station utilizes an indirect method of testing check valves VC8542A and B since these lines are not instrumented with flow or dif ferential pressure indicators. Total charging pump flow is calculated using measured pump dif ferential pressure and the manuf acturer's pump curve. Total pump flow includes flow through the pump discharge header and the mini-flow line. The flow rate through the mini-flow line is equal to the calculated flow f rom the pump curve minus the measured flow in the discharge header.
This method described above was verified to be accurate by installing temporary ultrasonic flowmeters on the mini-flow line and comparing this to the ca lculated f low.
1his alternative will provide adequate assurance that operational readiness is maintained.
4 234j 1057t 0505A
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Yalve Relief #24
'2elief is requested from full stroke exercising Reactor Coolant Pump Seal Injection Manual Valves VC8369A, B, C, 0 and VC8372A, B, C, 0 quarterly.
l Code Requirement IWV-3411 (test frequency)
Basis and Alternative Relief is requested f rom full stroke exercising manual valves VC8?69A, B, C, O and VC8372A,-B, C. O quarterly during operation of the reactor coolant pumps because this may damage the pump seals and would require re-adjusting the seal
_f low to the reactor coolant pump.
These valves will be full stroke' exercised during cold shutdown when reactor coolant pumps are secured. This alternative will provide adequate assurance of the required level of safety and that operational readiness is maintained.
234k i
1057t 0505A
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234m 1051t 0505A i
.. . l Valve Relief f27 i
Relief is requested from the exercising procedure requirements for full disk lift of Safety injection Check Valves S19001 A thru 0 and S19002 A thru D.
Code Requirement IWV-3529 (exercising procedure) l Basis and Alternative Relief is regaested to measure flow to check valves SI9001 A thru D and SI9002 A thru D by an indirect method to verify full disk lif t. During preoperational testing, dif ferential pressure gages were temporarily installed between check valves S19001 and S19002 inorder to calculate the ficw through each of the four SI cold leg lines. This testing demonstrated that flow was approximately equal through each line. Due to radiation concerns and the difficulty to 'istall the temporary dif ferential pressure gages because of physical parameters, Zion Station will assume that flow through each of the four 51 cold leg lines is still balanced. This assumption is based on the fact that if one of the check valves should become impaired, flow through this line would become obstructed and flow would become imbalanced through the four lines. This imbalance of flow would be indicated on the flow instrumentation located between the common RHR discharge header and check valves SIB 957A, B.
Zion Station is proposing that full disk lift will be verified for check valves S19001 A thru D and S19002 A thru D if the ratio of flow through this flow instrumentation is approximately equal to one. Specific acceptance criteria will be included with the test proced:Jre. If the ratio of flow does not meet this acceptance criteria then dif ferential pressure gages will be temporarily installed between check valves S19001 and SI9002 to determine which line is causing the imbalance of flow and the necessary corrective action will be taken.
These valves will be exercised for full disk lif t during cold shutdown because the RCS pressure will then be low enough to allow adequate flow through the check valves.
This alternative will provide adequate assurance of the required level of safety and that operational readiness is maintained.
234n 1057t 0505A
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4 Valve Relief #28 Withdrawn 2340
-1057t
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Valve Relief #29 i For valves required to be tested at cold iutdown, relief is requested to test these valves only whenever the plant it ir, cold shutdown condition for more l than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i
Code Requirement I-IWV-3412 (exercising procedure).
L Basis and Alternative For valves required to be tested at cold shutdown, relief is requested to test ,
these valves only whenever the plant is in cold shutdown condition for more ['
than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and testing not to interfere with the subsequent startup. Zion Station feels that it is undue hardship for the utility to test all valves when the unit goes to cold shutdown for a short repair. The testing would most probably increase the length of the cold shutdown and delay the subsequent startup causing the utility to have increased workload and lots of revenue. This request is based on discussions during the CECO /NRC meeting on Nov.15 and 16,1984 in Bethesda, Maryland.
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234p 1057t 0505A
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l Valve Relief #30 Withdrawn 234q l
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Valve Relief #31 ,
Relief is requested from the quarterly exercising requirements for the air sampling system return check valve PR0029.
Code Requirement IWV-3521 (test frequency).
Basis and Alternative -
1 Relief is requested'f rom the quarterly exercising requirement for the air sampling system return check valve PR0029 to the closed position. To test PR0029 quarterly would mean sending a person into containment while the reactor is operating. Also testing PR0029 to the closed position requires disassembling the air sample system inorder to provide a vent path.
Additionally the System Particulate, lodine and Noble Gas Monitor (SPING) is in continuous operation and returns air back to containment through check valve PR0029. Closing PR0029 would require that the SPING be secured and thus air samples of containment would have to be taken at a greater f requency and analyzed manually. Zion Station proposes to verify closure of check valve l
. PR0029 by leak testing at refueling outages. This alternative will provide adequate-assurance of the required level of safety and that operational readiness is maintained.
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Valve Relief #32
. Relief is requested from trending the stroke times of isolation seal water control valves.LCV-IWO1, LCV-1WO2 and PCV-1WO3.
Code Requirement .
i IWV-3417 (Corrective Action) ,
4 Basis and Alternative Relief is requested f rom trending the stroke times of LCV-IWO1, LCV-1WO2 and PCV-lWO3. These valves are not designed to actuate automatically, the valves-are stroked by disassembling a pipe fitting in the air supply line to bleed <
off the air. The stroke time is dependent on how fast or slow the fitting is disassembled. Therefore repeatable stroke times cannot be obtained. fhese valves shall be stroked quarterly and have a maximum stroke time assigned.
Titis will provide adequate assurance that operational readiness 'is maintained.
234s 1057t 0505A
s ., s
.s. o 1HIS PAGE WA5 INTENTIONALLY LLF1 BLANK 2341 1057t 0505A
- c, 6 4 .. j l
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i' ATTACHMENT A
' TYPICAL AIR OPERA 1ED VALVE TREND SHEETS' i
4 234u 1057t 0505A
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7 Mf T v432 m ,, _ce.,1 - 43,i l
ihh$hI$k$$$$$ b $ $ h $ $ k $ $ $ $$ b$$hI$k$b$$$ - e 0
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- a.- s Valve No.: 1ADV-559854A Maximum Stroke Time: 60 Seconds full Stroke Exercise Quarterly Remarks:
y 4 '
a A> M
- 3
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10^
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90 l
B0 70 N .uwu m. .a 50 ,
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234w SNIN
POWER OPERATED VALVE TRENDING Valve No.: 1A0V-RC8025 Maximum Stroke Tirae: 60 Seconds Full Stroke Exercise Quarterly Remarks: 10/84 stroke time increase >50%, believe 9/84 time low and 10/84 is in normal range, b,
Y b &. Q b q .
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100 1 90 I
1 80 70 - -
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50 1
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Valve No.: 1FCV-lWOB Haximum Stroke Time: 60 Seconds :
Full Stroke Exercise Quarterly Remarks:
M M N *
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I 90 l
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80 I
70 T
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40 l
30 I
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i, e4 t,Ss i, se-234y 1057t 0505A I
m _ _ _ _ _ - - ~ _ _ - - - - _ _ - - _
Valve No.: 2FCV-1W13 Maximum Stroke Time: 60 Seconds full Stroke Exercise Quarterly Remarks:
e
%' N $' N % N .
100 l
90 80 M
70 MOXiMwM 60 1
50 I
1 1
30 20 I
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5$ b$b$$ b$b $$$$$$$$h$$$ $$$$$$$l}$jj 84 - 1,85 ,, sc_
l 234z 1057t 0505A
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A..T..T.ACHMENT 4 l
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ATTACHMENT 4 REFERENCES Letter D.e.s_crip t ion (a) June 27, 1983 letter from CECO's initial submittal of Zion's F.G. Lentine to H.R. Denton 2nd Interval ISI/IST Program.
(b) May 11, 1984 letter from NRC's request for additional infor-S.A. Varga to D.L. Farrar mation (RAI) concerning ISI Program.
(c) June 22, 1984 letter from NRC RAI on both ISI and IST programs.
S.A. Varga to D.L. Farrar (d) June 26, 1984 letter from CECO's response to reference (b).
R.N. Cascarano to H.R. Denton f (e) August 14, 1984 letter from CECO's additional response to reference R.N. Cascarano to H.R. Denton (b) and submittal of Revision 1 to the ISI/IST program.
(f) January 2, 1985 letter from NRC's granting of interim relief.
S.A. Varga to D.L. Farrar (g) January 25, 1985 letter from Ceco's response to reference (c).
R.N. Cascarano to H.R. Denton Contained commitments for modifications and relief requests.
(h) February 11, 1986 letter from NRC's SER on ISI relief requests.
S.A. Varga to D.L. Farrar (1) May 13, 1985 letter from CECO submittal of Revision 4 relief P.C. LeBlond to H.R. Denton request to 1st interval.
(j) July 30, 1985 letter from NRC approval of reference (1).
S.A. Varga to D.L. Farrar (k) June 17, 1986 letter from CECO submittal of Revision 2 P.C. LeBlond to H.R. Denton to the ISI/IST program.
I (1) March 31, 1987 letter from NRC RAI regarding IST program.
J.A. Norris to D.L. Farrar (m) May 29, 1987 letter from CECO submittal of Revision 3 P.C. LeBlond to US NRC to the IST program.
I 3932K l
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______- _ - _ _ - - _ - - >