L-93-184, Forwards Second Ten Yr Inservice Insp Interval Inservice Testing Program
| ML17309A702 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/03/1993 |
| From: | Sager D FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17228A243 | List: |
| References | |
| L-93-184, NUDOCS 9308100124 | |
| Download: ML17309A702 (93) | |
Text
ACCEI ERAT DOCUMENT DIST UTION SYSTEM REGULAT INFORMATION DISTRIBUTIO STEM (RIDS)
ACCESSION NBR:9308100'3.24 DOC.DATE: 93/08/03 NOTARIZED: NO DOCKET I FACIL:50-389 St. Lucre Plant, Unit 2, Florida Power
& Light Co.
05000389 AUTH.NAME AUTHOR AFFILIATION SAGER,D.A.
Florida Power
& Eight Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards "Second Ten Yr Inservice Insp Interval Inservice Testing Program."
DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code NOTES:
(do RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: ACRS NRR/DE/EMEB NUDOCS-ABSTRACT OGC/HDS3 RES/DSIR/EIB EXTERNAL: EG&G BROWN,B NRC PDR COPIES LTTR ENCL 1
0 2
2 6
6 1
1 1
1 1
0 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DSP/ROAB NRR/EMCB O~Zgcg EG FILE 01 EG&G RANSOME,C NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
0 1
1 1
1 1
1 D
D A
D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 19
P.O. Box 128, Ft. Pierce, FL 34954-0128 AUG 0 3 1993 L-93-184 10 CFR 50.4 U.
S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.
C.
20555 RE:
St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
The second ten year in-service inspection interval for St. Lucie Unit 2 begins on August 8,
- 1993, and ends on August 8,
2003.
Pursuant to 10 CFR 50.55a(g)(4)(ii), the enclosed program outlines the IST plan for St.
Lucie Unit 2 based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code (ASME CODE),
1986 Edition.
Enclosure 1 is a
summary of the changes in the relief requests submitted in Revision 2 of the IST Program for the first ten year interval.
Enclosure 2 is a pen and ink mark up of the valve tables included in Revision 2 of the IST Program for the first ten year interval.
Enclosure 3 is Revision 0 of the St. Lucie Unit 2 IST Program for the second ten year interval.
Please contact us if there are any questions about this submittal.
Very truly yours, D. A.
Vice St.
L ger sident e Plant Enclosures (3)
DAS/GRM/kw cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant DAS/PSL f959-93 9308100124 930803 PDR ADOCK 05000389 8
P ah~
(,. rg(fQ
t St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
ENCLOSURE 1
Summary of Changes Between the St. Lucie Unit 2 IN-SERVICE TESTING Programs Revision 2 of the First Interval to Revision 0 of the Second Interval
St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
Summar of Chan es Between the St. Lucie Unit 2 IST Pro rams Revision 2 of the First Interval to Revision 0 of the Second Interva1 St. Lucie Unit 2 begins its second ten-year interval on 8 August 1993.
This document outlines the changes made to the program since the latest submittal.
Administrative changes, such as spelling or punctuation
- errors, or changes that do not change the original intent of the program will not be addressed.
In March 1993, St.
Lucie Plant personnel initiated an extensive review of the In-Service Test Program.
The review began by reviewing the scope of the systems included in the IST program.
A list of all Class pumps and valves was generated for each unit.
All of the pumps and valves in the lists were then evaluated per the criteria of the ASME Section XI Code.
Those pumps and valves that were exempt per IWP-1100, IWP-1200, IWV-1100, and IWP-1200 were deleted from the lists.
The pumps and valves that remained were then examined individually in detail.
Those pumps and valves that, were not required to perform a specific function in shutting down the reactor to the cold shutdown condition or in mitigating the consequences of an accident were also deleted from the lists.
Those pumps and valves that remained were placed in the IST program.
There were some Class pumps and valves in several systems that were not included in the final IST program list.
Examples of those systems include the instrument air system, diesel air start system, and diesel fuel oil system.
According to Regulatory Guide 1.26, these systems were not required to be built to Class 1,
2, or 3
standards.
The systems were built to Class standards at the option of FPL.
In accordance with IWA-1300(e), including the pumps and valves in these systems in the IST program was at the option of FPL and not a requirement.
Although the pumps and valves were not included in the final IST program, they are still tested regularly to demonstrate that they are able to perform their intended functions to meet the requirements of 10 CFR 50 Appendix B.,
In-Service Testin Pro ram Plan 1.0
==
Introduction:==
The introduction was changed to reflect the latest revision of the ASME Code.
The new IST program is based upon the requirements of Section XI of the ASME Boiler and Pressure Vessel
- Code, 1986 Edition.,
~
~
St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
2.0 Applicable Documents:
Item 2.6 was changed to reference Section XI of the ASME Boiler and Pressure Vessel
- Code, 1986 Edition.
4.4 Check Valve Testing:
The Non-Intrusive check valve testing has been included in this section.
St.
Lucie plans to investigate the use of these instruments in the full flow exercising and/or back flow testing of check valves.
4.7 Cold-Shutdown Testing The cold shutdown testing justification provided in Appendix E is not new; however, this reference to it is new.
A endix A
Pum Pro ram Tables Diesel Fuel Oil Transfer
- Pumps, 2A and 2B These pumps have been deleted from the IST program Low Pressure Safety Injection Pumps, 2A and 2B The tables have been modified to include the reference to PR-10 under the heading of vibration for these two pumps.
Due to vibration feedback from running reactor coolant pumps, vibration measurements will not be taken during cold shutdown testing if an RCP is running.
A endix B
Pum Pro ram Relief Re uests Relief Request No.
PR-2 Temperature measuring portable instruments have been deleted from this relief request.
Relief is no longer required for the temperature instruments due to the discontinuation of the yearly bearing temperature measurements per PR-2.
Relief Request No.
PR-3 This relief request has been deleted.
Although the Code does not specifically exempt the inlet pressure measurement when a pump is not running, the provision of IMP-3400(b) only requires taking those measurements performed at reference conditions, which does
t St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval
'In-Service-Testin Pro ram Revision 0
not include the inlet pressure measurement before pump start-up.
Therefore, when performing a test on a
pump that is already in operation, the only required inlet pressure measurement is the one taken with the pump operating at reference conditions and the requested relief was not necessary.
Relief Request No.
PR-7 Diesel Fuel Oil Transfer Pumps 2A and 2B have been deleted from the IST program.
Therefore, this relief is no longer required.
Relief Request No. PR-12 The Code requires that the frequency response of the vibration instrumentation shall be at from one-half minimum speed to at least maximum pump shaft rotational speed (IWP-4520).
The lower frequency response for the charging pumps, which operate at 210-215 rpm, is 1.75 Hz.
The present frequency response of St. Lucie's vibration instruments is 10 Hz.
At the time that these instruments were purchased several years
- ago, 10 Hz was the lowest frequency response available in commerci'al instruments.
The second interval PR-12 requests a
seven month interim until March 1994 to investigate these new instruments or to justify the continued use of the non-conforming instruments.
Relief Request No.
PR-13 The Code requires that the frequency response of the vibration instrumentation shall be at from one-half minimum speed to at least maximum pump shaft rotational speed (IWP-4520).
The lower frequency response for the intake cooling water
- pumps, which operate at 885 rpm, is 7.38 Hz.
The present frequency response of St. Lucie s vibration instruments is 10 Hz.
At the time that these instruments were purchased several years ago, 10 Hz was the lowest frequency response available in commercial instruments.
The second interval PR-13 requests a
seven month interim until March 1994 to investigate these new instruments or to justify the continued use of the non-conforming instruments.
Relief Request No.
PR-14 The Code requires that the frequency response of the vibration instrumentation shall be at from one-half minimum speed to at least maximum pump shaft rotational speed (IWP-4520).
The lower frequency response for the hydrazine
- pumps, which operate at 37 rpm, is 0.31 Hz.
The low frequency vibration of these pumps is
St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval Xn-Service-Testin Pro ram Revision 0
considered to be relatively insignificant.
Any binding or excessive bearing wear within these pumps would be discovered by audible noise or excessive vibration at the driver and reduction gearing.
The second interval PR-14 requests a
seven month interim until March 1994 to investigate these new instruments or to justify the continued use of the non-conforming instruments.
Relief Request No.
PR-16 Diesel Fuel Oil Transfer Pumps 2A and 2B have been deleted from the IST program.
Therefore, this relief is no longer required.
A endix C
Valve Pro ram Tables Test Frequency Test frequency "RF" has been updated to reflect the change 'o ANSI/ASME OM-1-1981 for relief valve testing.
A endix D
Valve Pro ram Re uests for Relief Relief Request VR-2 The Alternate Testing 'ectioh was modified to conform to the requirements in the Technical Specifications Table 3.4-1 and the conditions under which the tests could be performed.
The Technical Specification was only applicable to Modes 1,
2, 3,
and 4;
therefore, part 5
of the Alternate Testing section which addressed Modes 5
and 6,
was dropped.
Testing of these check valves will continue to be performed in accordance with the Technical Specification.
Relief Request VR-5 For cold shutdown testing, these check valves are flow exercised while borating the RCS for shutdown margin.
There are conditions under which flow testing of these valves is not prudent and would constitute an undue burden upon the plant.
An example of such an event would be a rapid plant shutdown (i.e., plant casualties) where pausing for testing would not be appropriate.
Therefore, the second interval VR-5 requests that when plant conditions exist that make cold shutdown testing impractical that relief from such testing is granted.
St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
Relief Request No. VR-9 This relief has been updated to include more detail on the available flow paths that could be use for partial-exercising of these check valves and the reasons why each one cannot be used for quarterly test.
The frequency for the partial-exercise test was changed from "as plant conditions warrant" to once each cold shutdown per VR-1.
Relief Request No. VR-10 This relief has been updated to include more detail on the available flow paths that could be use for partial-exercising of these check valves and the reasons why each one cannot be used for quarterly test.
Partial-exercise and closed tests were added for once each cold shutdown per VR-1.
Relief Request No. VR-11 This relief has been updated to include more detail on the available flow paths that could be use for partial-exercising of these check valves and the reasons why each one cannot be used for quarterly test.
The frequency for the partial-exercise test was changed from "as plant conditions warrant" to once each cold shutdown per VR-l.
Relief Request No. VR-12 This relief has been updated to include more detail on the available flow paths that could be use for partial-exercising of these check valves and the reasons why each one cannot be used for quarterly test.
Partial-exercise and closed tests were added for once each cold shutdown per VR-l.
Relief Request No. VR-17 Revision 2 of the first interval was not required since the valves would be tested during cold shutdowns.
This relief request was withdrawn from the second interval IST submittal.
Relief Request No. VR-18 The second interval VR-18 has changed the test period from cold shutdown to a Refueling Outage test in conjunction with Appendix Z testing.
The only practical means of verifying closure is by performing a leak test or back flow test.
Performing such a test demands that the make-up water supply line be isolated.
This
St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
effectively isolates the entire supply of fire water to the containment which is unacceptable under any plant conditions.
Thus, prior to leak testing in this manner an alternate firewater source must be established by rigging several temporary fires hoses through the maintenance hatch to the various fire fighting stations in the containment building.
This is not possible during normal operation when primary containment is required and would constitute an undue burden on plant personnel during cold shutdowns.
Relief Request No. VR-19 The Alternate testing frequency was changed from "every 2 years" to once every refueling outage.
Relief Request No. VR-22 Following a Recirculation Actuation Signal, the suction of the safety inject'ion pumps is changed from the refueling water tank to the containment sump.
The RAS also stops all running low pressure safety injection pumps.
Therefore, the maximum expected flow through one of the containment sump check valves would be one high pressure injection pump and one containment spray pump.
The LPSI pump listed in the Basis For Relief section has been deleted.
Relief Request No. VR-25 Revision 2 of the first interval was not required since the valves would be tested during cold shutdowns.
This relief request was withdrawn from the second interval IST submittal.
Relief Request No. VR-26 Diesel Generator Air Start systems have been deleted from the IST program.
Therefore, this relief is no longer required.
Relief Request No. VR-28 The back flow test for these two check valves has been changed from cold shutdown to quarterly.'elief Request No. VR-30 St. Lucie Unit 2 was granted a one time relief from the disassembly and inspection of these check valves.
The relief required that both check valves must be inspected during the following refueling outage.
Originally, the next outage was scheduled for the Fall of
St. Lucie Unit 2 Docket No. 50-389 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
- 1993, however, due to unscheduled
- outages, the next refueling has been rescheduled for the Winter of 1994.
This relief request has been changed to reflect this.
Relief Request No. VR-31 The original relief request listed the full flow testing frequency as once each refueling outage.
The second interval VR-31 has increased the frequency to once each cold shutdown per VR-1.
St. Lucie Unit 2 Docket No.
5 0-3 8 9 Second Ten-Year In-Service Inspection Interval In-Service-Testin Pro ram Revision 0
ENCLOSURE 2
PEN 6 INK M2QtK UP VALVE TABLES
~ 9308100124
t
Appendix C
Valve Program Tab FQRINFQRY'"< '
Q THIS OOCUfrIENT IG V 47ROL O.
". U VERIFY INFORMATK Mr TH NTRO' OO l'RENT FLORID f
'. 'I=AAr'!
IG
'"~ 'B 'I
. '.UCIE VFRIFIEO '
OATE 06029
Revision 2
08/01/92 Florida Power
& Light Company INSERVICE TESTING VALVE TABLES St. Lucie Nuclear Plant - Unit 2 PAGE 1
LEg~E VALVE NUMBER The plant alpha-numerical subject valve nator for the COORD The coordinate location designated drawing the valve on the CL CAT SIZE TYPE A/P The va The tiv A) p v
'v I
2 The ISI Classific respective ISI boun The valve cate ry The valve'nal ty ion the valve as per the rawings er agraph IWV-2200 e i inches sive (P) determination for the ACT. TYPE MO MAN PO S/A SO y3.ve a or type as follows:
Air-operated Diaphram-operated Electric motor-operated Manual valve Piston-operated Self-actuated Solenoid-operated NORM POS.
REM IND FAIL QODE Designates the normal position of the valve during plant operation at power Notes if a valve has remote position indication Identifies the failure mode (open or closed) for a valve.'AI indicates the valve fqil~s-s".
Fog (P)fQI3~]j$ I I"~tg Ql 4L <
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FLOR/DA POOF P. AI~IO L
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NUCL~>R FhEPG'i'T LUQIEPQ~NT DATE VERIFIED SV OGOP9p
Revision 2
08/01/92 Forida Power
& Light Company INSERVICE TESTING VALVE TABLES St. Lucie Nuclear Plant - Unit 2 PAGE 2
Identifies the test require ts for a valve as follows:
CV/C CV/0 CV/PO EC EE EO INSP PEC PI SLT-1 SLT-2 SLT-3 SRV Check valve exer J.y to closed position.
Check valve ull-8 oke exercise to open position.
Check v 8ve p
ial-stroke exercise to open posx ho Exer t
c
~ sed position.
For all cate ry r
me l
be measured unless de n a ociated relief request.
rb e
e to verify proper operation a
o 'gg with no stroke time meas t ~
Requires observation of yst pa meters or local observation of v 8~
ation.
er se to open position; For all e
ry A or B power-operated valves st, e
times will be measured unless excluded by an associated relief request.
Fail safe test Disassembly and inspection of check valves Partial closure exercise for power-operated valves Position indication verification Selt leakrate test per 10 CFR 50, App J Seat leakrate test for pressure isolation valves.
Seat leakage test of air accumulator check valves.
Set point, check for safety/relief valves Fgg II~I~Q'lAI QN ONL(
TFIIS OOCUIAEtIT!S 7'OT CG)VitiQI.LEI).GEFG!IE USE, VERIFY I<<FOIIi'PATIOS Vi'ITHA CG)'STROLLED OOCUMEI'6'LOPIDA POVJFR P ND LIGHTCO NUCLEAR ENERG'I'T.
LUCIE PLANT
/
VEAIFIEDDY DATE 06027
Revision 2
08/01/92 Florida Power
& Light Company INSERVICE TESTING VALVE TABLES St. Lucie Nuclear Plant - Unit 2 PAGE 3
TEST FREQ The required test interval s
l ws:
QR CS 2Y RF SP Quarterly (during pl Cold shutdown as Specification Every 2 years Each reactor qguel case where safety/re e
v e
IWV-3510-Other 4 e operation)
Ie ined by Technical g outage (cycle).
In the is designated for refer, to Table equest for Relief)
RELIEF REQ Refers with D) 4' spa@a dirac 0 s relief request associated requirement.
(See Appendix FOR IIKIFOI'.l::.l,'iTK490:;<If y VERlrR'INI'ORi'i'lATIOMVi'ITIIh COtiTROLL.D DOCUK'iEÃT FLORIDA PO'.V~iR AND LIGHTCO.
RUCL&I=.lRFf'c ERGY ST. LUCIE PLhi'ii
/
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2 VALVE TABLES DATE
- 08/01/92 Saint Lucia Nuclear Plant - Unit 2 PAGE 4
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2 DATE
- 08/01/92 PAGE 6
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SIZE TYPE A/P TYPE POS.
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C 3.000 SAFETY A
S/A C
NO SRV RF V-1201 G.6 1
C 3.000 SAFETY A
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NO SRV RF V-1202 G-6 1
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2 VALVE TABLES DATE
- 08/01/92 Saint Lucie Nuclear Plant - Unit 2 PAGE 7
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DO 0
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2 DATE
- 08/01/92 PAGE 8
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CL CATE SIZE TYPE A/P TYPE POS.
IND MODE EXAM FREQ REQ.
REMARKS FCV-2210Y C-2 2
8 1.000 GLOBE A
00 C
YES FC EC QR FS QR Pl 2Y V-2177 C-3 2
C 3.000 CHECK A
S/A C
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S/A C
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2 DATE
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ACT.
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CL CAT.
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IND HDDE EXAH FREQ REQ.
REHARKS V-3457 V-3463 V-3495 F-2 2
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2 DATE
- 08/01/92 PAGE 18 CCCRRSCRSRSscascassssc5555555555accccsassSRCCZRSSSSRZRSRSRRRRZSRSSSSCSSSSCSSRCR 555555sCCRRRSZSRCSZSsss P
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SYSTEH:
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2 DATE
- 08/01/92 PAGE 19 sasasacsscsssssaaaarrscsrssassaasssacaaaasasssaaassaassacaccaccsasasssssasrasssasasaraasaasarcrssc rasa P 8 I0$ 2998-G-078 SH 132 SYSTEH$
SAFETY INJECTION SYSTEH saacraaasssaaccsaaarrasaaass asasaaaaasaasrsassaacscaassracrsrssssassssassaassssrsaarrsrssacs aacrrsrs ACT.
NOR}I REH FAIL TEST RELIEF VALVE HUHBER COORD.
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2 DATE
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2 DATE: 08/01/92 PAGE t
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- 08/01/92 PAGE 41 xxaxxxaxassaa a
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2 DATE
- 08/01/92 PAGE 43
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2 DATE
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REHARKS FCV-26.1 G-2 2
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2 DATE: 08/01/92 PACE 45 saris cs riiiirsaiascscsssscar carr
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2 DATE
- 08/01/92 PAGE 50 srrarssas asasraa arrraaassaaasrraarrararassssssaassaraara srasaarrassa
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NO CV/C CS CV/0 CS SLT-1 2Y VR-16 THIS DOCu><ENT IS XOT COr TROLLED. BEFORE uSE, VERIFY INFORM,'AT:ONWITHA CONTROLLED DOCUMENT FLORIDAPOWER AND LIGHTCO.
NUCLEAR ENERGY ST. LLICIEPLANT
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VERIFIED BY DATE OG0292
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2 DATE
- 08/01/92 PAGE 51 xasssssssasssasxasxssasaca xxaaacssxs x ss ssssssssaasssaaxsaasssaaaxsscaaccaaaasasxasssssssssss crass P
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2 DATE
- 08/01/92 PAGE 53 aaaaraaaasaasssssss aasraaasaaaasarr r
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SYSTEH:
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REHARKS FCV.25-34 N-2 2
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RUCI EAR ENERGY ST. LUCIE PLANT VERIFIED BY DATE OG0292