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| issue date = 08/02/1985 | | issue date = 08/02/1985 | ||
| title = Forwards marked-up Draft Tech Specs,Per Util 850712 Commitment.Corrections,Comments,Graphs,Tables,Figures & Justifications Included.Meetings to Resolve Issues or Questions Scheduled for 850805 & 06 at NRC | | title = Forwards marked-up Draft Tech Specs,Per Util 850712 Commitment.Corrections,Comments,Graphs,Tables,Figures & Justifications Included.Meetings to Resolve Issues or Questions Scheduled for 850805 & 06 at NRC | ||
| author name = | | author name = Van Brunt E | ||
| author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR | | author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR | ||
| addressee name = | | addressee name = Knighton G | ||
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | ||
| docket = 05000529 | | docket = 05000529 | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:g C', c REGULATORY li FORMATION DISTRIBUTION | {{#Wiki_filter:g C', | ||
NO DOCKET FACIL:STN 50 529 Palo Verde Nuclear Stationr Unit 2g Arizona Publi 05000529 AUTH, NAME AUTHOR AFFILIATION VANBRUNT''.E | c REGULATORY li FORMATION DISTRIBUTION SY M (RIDS) | ||
~Arizona Publ ic Ser vice'o, RECIP~NAMEI RECIPIENT AFFILIATION | ACCESSION NBR!8508050402 DOC ~ DATE: 85/08/02 NOTARI2ED: NO DOCKET FACIL:STN 50 529 Palo Verde Nuclear Stationr Unit 2g Arizona Publi 05000529 AUTH, NAME AUTHOR AFFILIATION VANBRUNT''.E~ Arizona Publ ic Ser vice'o, RECIP ~ NAMEI RECIPIENT AFFILIATION KNIGHTON g*G ~ Pl ~ Licensing Branch 3 | ||
==SUBJECT:== | ==SUBJECT:== | ||
Forwards marked-up draft Tech Specs<per util.850712 commitment~Corrections<comments<graphsitablesrfigures'8 Justifications included.Meetings to resolve issues or~Questions scheduled for.850805 L 06 at NRG~AJ DISTRIBUTION CODE: B001D COPIES RECEIVED:LTR | Forwards marked-up draft Tech Specs<per util.850712 commitment~Corrections<comments<graphsitablesrfigures'8 Justifications included. Meetings to resolve issues or~ | ||
Questions scheduled for. 850805 L 06 at NRG ~ | |||
PSAR/FSAR Amdts 8 Related Correspondence NOTES:Standardized plant.05000529 RECIPIENT ID CODE/NAME. | AJ DISTRIBUTION CODE: B001D COPIES RECEIVED:LTR . | ||
NRR/DL/ADL-NRR LB3 LA | TITLE: Licensing Submittal: PSAR/FSAR Amdts 8 Related Correspondence NOTES:Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT , COPIES ID CODE/NAME. LTTR ENCL= ID CODE/NAME LTTR ENCL< | ||
NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DSI/CPB 10.NRR/DSI/ICSB 16 NRA/DSI/PSB 19 NRR/DSI/RSB 23 | NRR/DL/ADL-NRR LB3 LA 1 | ||
1 0 0 NRR LB3 LICITRArE BC 01 1 | |||
1 0 | |||
1 INTERNAL ACRS 41 6 ADt1/LFMB 1 0 ELD/HDS3 1 0 IE F ILE. 1 1 IE/DEPER/EPB 36 1 1 IE/DQAVT/QAB2'1 1 1 NRR ROErM ~ L. NRR/DE/AEAB 0 NRR/DE/CEB NRR/DE/EQB il 13, 1 | |||
1 2 | |||
1 1 | |||
2 NRR/DF/EHEB NRR/DE/GB 28 1 | |||
1 2 | |||
1 2 | |||
NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 24 1 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFEB40. 1 1 NRR/DHFS/LQB 32 1 1>> | |||
NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0. | |||
NRR/DSI/AEB 26 1 1 NRR'/DSI/ASB 1 1 NRR/DSI/CPB 10. 1 1 NRR/DSI/CSB 09 1" 1 NRR/DSI/ICSB 16 1 1 NRR/DSI/METB 1 1 NRA/DSI/PSB 19 1 1 /RAB 22'4 12'RR/D 1 1 NRR/DSI/RSB 23 1 1 1 1 RGN5 3 3 RM/ /MIB 1 0. | |||
J EXTERNAL: 24X DMB/DSS (AMDTS) | |||
NRC>> PDR PNL" GRUEL'gR 02". | |||
1 1 | |||
1 1 | |||
1 1 | |||
1 LPDR,' | |||
IC .'5 BNL(AMDTS ONLY) 03"'S 1 | |||
1 1 | |||
1 1 | |||
1" TOTAL NUMBER OF COPIES REQUIRED>>'TTR 52 ENCL | |||
t 1 0 0 A a | |||
ll Pt a | |||
Arizona Nuclear Povver ProJect P.O. SOX 52034 o PHOENIX, ARIZONA85072-2034 Mr. George W. Knighton, Chief ANPP-33162-EEVB/JRP Licensing Branch No. 3 August 2, 1985 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 | |||
==Subject:== | ==Subject:== | ||
Palo Verde Nuclear Generating Station Unit 2 Docket No.50-529 Plant Technical Specifications (Draf t)File: 85-055-026 | Palo Verde Nuclear Generating Station Unit 2 Docket No. 50-529 Plant Technical Specifications (Draf t) | ||
File: 85-055-026 | |||
==Reference:== | ==Reference:== | ||
: 1) Letter from G. Knighton, NRR, to E. E. Van Brunt, ANPP, dated June 21, 1985 | |||
: 2) Letter from E. E. Van Brunt, ANPP, to G. Knighton, NRR, dated July 12, 1985 | |||
==Dear Mr. Knighton:== | |||
Reference 1 transmitted to ANPP a "Draft" copy of PVNGS Unit 2 Technical Specifications. ANPP was to review this draft and make appropriate comments and changes. By copy of Reference 2, ANPP supplied the first set of comments along with a revised schedule as to the need date of Unit 2 Tech. Spec. | |||
issuance. We also identified that marked up tables, graphs and figures would be supplied by August 15, 1985. | |||
By copy of this letter, all the corrections, comments, graphs, tables and figures for PVNGS Unit 2 Tech. Specs. and their justifications are being transmitted to you. Meetings to resolve these issues, or any questions, are to be held August 5 and 6, 1985, in your offices. | |||
The next step is the issuance and review of the PVNGS Unit 2 proof and review. | |||
8508050402 850802 PDR ADOC'K 05000529 g A PDR | |||
<<I II I, <<f l<< | |||
II I, | |||
I II 5 I. | |||
Mr. George W. Knighton, Chief U. S. Nuclear Regulatory Commission Page Two ANPP-33162-EEVB/JRP If you have any questions, please contact me. | |||
Very truly yours, GLA~ | |||
E. E. Van Brunt, Jr. | |||
Executive Vice President Prospect Director EEVB/SRF/)le cc: Director, Region V, USNRC E. A. Licitra R. P. Zimmerman S. Brown | |||
Justifications For Enclosed PVNGS Unit 2 Tech. Spec. Changes The following pages contain administrative changes such as typographical and unit specific number changes. | |||
Index VIII Add Cathodic protection to 3/4 8.1. | |||
pg. 3/4 3-5 Action 2 Change 6.5.1.6.h to 6.5.1.6.G. There is not an Item h. | |||
Index XIII Add Cathodic protection pg. 3/4 1-21 Item C2a add Figure 3.1.2a. | |||
pg. 3/4 3-12 Delete the last 2 sentences in the 8$/ Footnote. Table 3.3-2a does not exist. The table for the CPL addressable constants was deleted for all CE units. | |||
pg. 3/4 3-13 Delete reference to Footnote 9 for Item C.2 "Channel Functional Test." The old footnote is deleted and the new footno'te doesn't apply to CPC's. | |||
pg. 3/4 3-14 Item III.A. "Channel Functional Test" change Footnote 10 to 9. Footnote 10 does not exist. | |||
pg. 3/4 3-15 Delete old Footnote 9 because the 2.2.2 Tech. Spec. no longer exists. Change Footnote 10 to 9. | |||
3-49 Typo's, unit specific numbers and added verbage for PS'g 3/4 3-50 switch identification. | |||
Pg. 3/4 3-51 Pg. 3/4 3-52 3/4 3-53 PS'S'g. 3/4 3-54 PS'S'/4 3/4 3-64 3/4 6-30 3/4 7-42 | |||
il l | |||
l | |||
pg. 3/4 7-41 Action b. Delete "...In recirculation Mode..." and add the word "operation" in its place. This is a typo. When action A was changed between Unit 1 Low Power License and Full Power License the change to Action b. was not made. | |||
,pg. 3/4 8-3 Delete Item B and use insert. This brings our Spec. into compliance with the previously approved McGuire Spec. | |||
which was an agreed position between NRR and ANPP during PVNGS Unit 1 Pull Power License changes. Footnote 0 Remove "This". | |||
pg. 3/4 8-5 Delete Item 5 This is replaced with Item C.2 on pg. 3/4 8-3a. | |||
Change Item d to e Typo. | |||
8-7 Change Items g to f and f to g Typo. | |||
3/4 8-16 Typo's, unit specific numbers and added verbage for over-PS'S'S'g. | |||
3/4 8-23 current devices. | |||
3/4 8-24 3/4 8-26 3/4 8-27 3/4 8-28 3/4 8-29 3/4 8-34 3/4 8-35 3/4 8-37 3/4 8-38 3/4 PS'S'S'S'S'S'S'S'S'S'S'S'S'S'S'S'/4 8-39 3/4 8-40 3/4 8-43 3/4 8-44 3/4 8-45 3/4 8-46 3/4 8-47 3/4 8-48 3/4 8-49 | |||
n a t'P n | |||
1 | |||
~, | |||
t | |||
pg. 3/4 8-8a Cathodic Protection Add this Spec. to be consistent with 'Unit l. | |||
pg. 3/4 9-1 Change 40 gpm in action statement to 26 gpm. This is to be consistent with changes made in 4.1.2.2.b. | |||
pg. 3/4 10-1 Same as above. | |||
pg. B3/4 3-4 3/4.6.5.1 should be changed to 3/4 6.4.1. | |||
The following graphs are being supplied for the PVNGS Unit 2 Tech. Specs. | |||
pg. 3/4 1-5 pg. 3/4 1-12 pg. 3/4 1-23 pg. 3/4 1-24 pg. 3/4 1-31 pg. 3/4 1-32 pg. 3/4 2-6 pg. 3/4 2-7 pg. 3/4 2-10 pg. 3/4 3-10 pg. 3/4 4-28 pg. 3/4 4-30 pg. 3/4 7-26 pg. B3/4 4-10 pg. B3/4 5-2 pg. B3/4 5-3 pg. B3/4 5-4 pg. B3/4 6-3 pg. B3/4'-4 pg. 3/4 3-29 Item 10 Add H "180+/180+*H" "H The response time for monitors XJ-SgA-RU-29 and XJ-SgB-RU-30 to trip on radiation is not included in the response time measurements for dampers M-HJA-MOl, M-HJA-M52, M-HJB-M01 and M-JHB-M55." | |||
This clarifies that the monitors are not included in the response time measurements for dampers. | |||
r- | |||
"i E | |||
I, II I | |||
pg. 3/4 3-6 Add "5 of" to action statements A and B. | |||
a "...per hour at 5 of the ..." | |||
b "...per hour at 5 of the ..." | |||
These additions are to bring Spec. 3.3.3.7 in agreement with Spec. 4.6.1.5. | |||
pg. 3/4 3-74 Replace Action 37 with insert. This change is being made to bring the Tech. Spec., Preplanned Alternate Sampling Program and Region V desires into compliance. | |||
pg. 3/4 6-12 Make noted changes in Table 4.6-1 to bring PVNGS Unit 2 Tech. Specs in compliance with Reg. Guide 1.35 Section C.1.3 and C.3. | |||
pg. 3/4 6-15 Suxveillance 4.6.2.1.6. Change 273 psid to 275 psid. | |||
T11is change is based on test data. | |||
pg. 3/4 3-22 Item IX deleted 8 under applicable modes. This footnote is no longer applicable. | |||
pg. 3/4 3-23 Delete footnote No longer applicable. | |||
pg. 3/4 7-41 Change hydrant numbers as shown. These are unit specific. | |||
pg. B3/4 4-8 Change numbers as shown to make applicable to Unit 2. | |||
pg. 3/4 3-36 Delete CIASA K205 CIASB K205 as per recent design change. These are now spares. | |||
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.85080504a2 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 7 PLANT SYSTEMS 3/4. 7..1 TURBINE CYCLE SAFETY VALVES................................. ~ ~ ~ ~ ~ ~ ~ 3/4 7"1 AUXILIARY FEEDMATER SYSTEH..................... 3/4 7-4 CONDENSATE STORAGE TANK............-........-. 3/4 7-6 3/4 7-7 MAIN STEAM LINE ISOLATION VALVES.............. 3/4 7-9 ATMOSPHERIC DUMP VALVES............-.-.-.-...- 3/4 7-10 3l4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.. 3/4 7-11 3/4..7. 3 ESSENTIAL COOLING MATER SYSTEH................... 3/4 7"12 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM.......................... 7-13 3/4.7. 5 ULTIMATE HEAT SINK.................................. 3/4 7-,.14 3/4.7. 6 ESSENTIAL CHILLED MATER SYSTEM...................... 3/4 7-15 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM............ 3/4 7-16 3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM............ 3/4 7-19 3/4o 7o 9 SNUBBERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3l4 7-21 3/4.7.1O SEALED SOURCE CONTAMINATION.................. 3/4 7-27 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION MATER SYSTEM....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-29 SPRAY AND/OR SPRINKLER SYSTEMS...... 0 ~ ~ ~ 3/4 7-32 C02 SYSTEMS.......................... 3l4 7-35 FIRE HOSE STATIONS ~ ~ ~ ~ ~ ~ ....-3/4 7" 37 YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES. 3/4 7-40 HALON SYSTEMS.................. 3/4 7-42 3/4.7.12 FIRE-RATED ASSEMBLIES...........;................... ~ ~ ~ ~ 3/4 7-43 3/4.7.13 SHUTDOWN COOLING SYSTEM....,.............. - - - .. -... -. ~ ~ ~ ~ 3/4 7"45 3/4.7. 14 CONTROL ROOM AIR TEMPERATURE...... -... - . - - - - .. - .. - . ~ ~ ~ 0 0 3l4 7-46 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES OPERATING.. 3/4 8"1 SHUTDOWN;.. 3/4 8-8 | |||
~~D~.PACKS':VXO~ . $ 3~$ | |||
PALO VERDE - UNIT 2 VIII | |||
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0 | |||
INOEX BASES SECTION ~ | |||
PAGE 3/4.7 PLANT SYSTEMS 3/4.7. 1, TURBINE CYCLE......'.......-....... -... - .. -..... B 3/4 7-1 3/4.7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION......... B 3/4 7-3 3/4.7..3 ESSENTIAL COOLING WATER SYSTEM.......................... B 3/4 7-3 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM........,...............-..>>.. B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK...................................... B 3/4 7-4 3/4 7o6 ESSENTIAL CHILLED WATER, SYSTEM.......................... B 3/4 7-4 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM................ B 3/4'7-5 3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM................ B 3/4 7-5 3 /4.7. 9 SNUBBERSo ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ o ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION............................. B 3/4 7-7 3/4.7.11 FIRE SUPPRESSION SYSTEMS....................,............. B 3/4 7-7 3/4.7.12 FIRE"RATED ASSEMBLIES........... B 3/4 7-8 3/4.7.13 SHUTDOWN COOLING SYSTEM............. B 3/4 7"8 3/4.7.14 CONTROL ROOM AIR TEMPERATURE............................ B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2', and 3/4.8.3 .A.C. SOURCES, D.C. SOURCES, and | |||
~ OHSITE POWER DISTRIBUTION SYSTEMS........:....... B 3/4 8-1 3/4.8.4 ELECTRICAL EgUIPMEHT PROTECTIVE DEVICES................. B 3/4 8-3 3/4. 9 REFUELIHG OPERATIONS 3/4o go 1 BORON CONCEHTRATIONo ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 9-1 3/4. 9. 2 INSTRUMENTATION.... B 3/4 9-1 3/4. 9. 3 DECAY TIME........ B 3/4 9-1 1 | |||
3/4. 9. 4 CONTAINMENT BUILDING PEHETRATIONS. B 3/4 9-1 3/4. 9. 5 COMMUNICATIONS B 3/4 9-1 PALO VERDE " UNIT 2 XIII | |||
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REACTIVITY CONTROL SYSTEMS 3/4. 1. 3 MOVABLE CONTROL ASSEMBLIES CEA POSITION LIMITING.CONDITION FOR OPERATION | |||
: 3. 1.3. 1 All full-length (shutdown and regulating) CEAs, and all part-length CEAs which are inserted in the core, shall be OPERABLE with each CEA of a given group positioned within 6.6 inches (,indicated position) of all other CEAs in its group. In addition, the position of the part length CEAs Groups shall be limited to the insertion limits shown in Figure 3. 1-2A. | |||
APPLICABILITY: MODES 1" and 2". | |||
ACTION: | |||
: a. With one or more full-length CEAs inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour and be in at least HOT STANDBY within 6 hours. | |||
: b. With more than one full-length or part-length CEA inoperable or misaligned from any other CEA in its group by more than 19 inches (indicated position), be in at least HOT STANDBY within 6 hours. | |||
C. With one or more full-length or part-length CEAs misaligned from any other CEAs in its group by more than 6.6 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with Figure 3. 1-2B and that within 1 hour the misaligned CEA(s) is either: | |||
: 1. Restored to OPERABLE status within its above specified alignment requirements, or | |||
: 2. Declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3. 1. 1. 1 is satisfied. After declaring the CEA(s) inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3. 1.3.6 provided: | |||
a) Within 1'hour the remainder of the CEAs in the group with the inoperable CEA(s) shall be aligned to within 6.6 inches of the inoperable CEA(s) while maintaining the allowable CEA sequence and insertion limits shown on Figures 3. 1-3 a | |||
: 3. 1-4; the THERMAL POWER level shall be restric ed pur-suant to Specification 3. 1.3.6 during subsequent operation. | |||
3 "See Special Test Exceptions 3. 10.2 and 3. 10.4. | |||
'ALO VERDE - UNIT 1 3/4 1-21 | |||
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1) | TABLE 3.3-1 Continued) | ||
TABLE NOTATIONS "With the protective system trip breakers in the"closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel. | |||
8The provisions of Specification 3.0.4 are no applicable. | |||
(a) Trip may be manually bypassed above 10-4X of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10-~X of RATED THERMAL POWER. | |||
(b) Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia. | |||
(c) Trip may be manual.ly bypassed .below lX of RATED THERMAL POWER; bypass shall'e automatically removed when THERMAL POWER is greater than on equal to. 1X of RATED THERMAL POWER. | |||
(d) Trip may be bypassed during testing pursuant to Special Test Exception | |||
: 3. 10. 3. | |||
(e) See Special Test Exception 3.10.2. | |||
(f) There are four channels, each of. which is comprised of one of the four reactor trip breakers, arranged in a selective two-out-of-four configuration (i.e., one-out-of-two taken twice). | |||
ACTION STATEMENTS ACTION 1 With the number'f channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next, 6 hours and/or open the protective system trip breakers. | |||
ACTION 2 With the number of channels OPERABLE one less than tne- Tota'l | |||
.Number'i': .Channels STAFTUP and/"<'OWER OPERATION may. conti i-provided the inoperable channel is placed in the bypassed or tripped condition .within 1 hour. If the inoperable channel is bypassed, the desirabi.lity of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5:1.6.j('he channel ehail be returned to OPERABLE status no later than during the next COLD SHUTDOWN. | |||
PALO VERDE - UNIT 2 3/4 3-5 | |||
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TABLE 3.3-2 (Continued) | TABLE 3.3-2 (Continued) | ||
REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME II.RPS LOGIC A.Matrix Logic B.Initiation Logic III.RPS ACTUATION DEVICES A.Reactor Trip Breakers B.Manual Trip | REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME II. RPS LOGIC A. Matrix Logic Not Appl icable B. Initiation Logic Hot Applicable III. RPS ACTUATION DEVICES A. Reactor Trip Breakers Not Applicable B. Manual Trip Not Applicable Neutron detectors are exempt from response time testing. The response time of the neutron flux signal portion of the channel shall be measured from the detector output or from the input of first electronic component in channel.. | ||
If the RTD time constant for a CPC channel exceeds the value corresponding to the penalties currently in use, the affected | Response time shall be measured from the output of the sensor. Acceptable CEA sensor response shall be demonstrated by compliance wi'th Specifica-tion 3.1.3.4. | ||
OThe pulse transmitters measuring pump speed are exempt from response time testing. The response time shall be measured from the pulse shaper input. | |||
¹¹Response time shall be measured from the output of the resistance temperature detector (sensor). RTD response time shall be measured at least once per 18 months. The measured response time of the slowest RTD shall be less than or e 3 secon A gus ments to t e C a ressa e constants given in Table 3.3-2a s all be made to accomodate current values of the RTD time constants. If the RTD time constant for a CPC channel exceeds the value corresponding to the penalties currently in use, the affected be declared inoperable until penalties appropriate to the new time channel(s)'hall constant re installed. | |||
¹¹¹Response time s a 1 be measured from the output of the pressure transmitter. | ¹¹¹Response time s a 1 be measured from the output of the pressure transmitter. | ||
The transmitter response time shall be less than or equal to 0.7 second., PALO VERDE-UNIT 2 3/4 3-Z2 | The transmitter response time shall be less than or equal to 0.7 second., | ||
PALO VERDE - UNIT 2 3/4 3-Z2 | |||
TABLE 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS | |||
( | |||
m CD m CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE VIREO Z | |||
M I. TRIP GENERATION A. Process | |||
: 1. Pressurizer Pressure - High S R M 1 2 2. | |||
1 Pressurizer Pressure - Low S R M 1 2 | |||
: 3. Steam Generator Level - Low S R M 1$ 2 | |||
: 4. Steam Generator Level - High S R M 11 2 | |||
: 5. Steam Generator Pressure - Low S R M g 1 2 3)k | |||
: 6. Containment Pressure - High S R M' 1 2 | |||
: 7. Reactor Coolant Flow - Low S R 1 2 | |||
: 8. Local Power Density - High S' D (2, 4), R (4, 5) M, R (6) 1$ 2 | |||
: 9. DNBR " Low 0 (2, 4), R (4, 5) M, R (6) 1 2 M (S), S (7) | |||
B. Excore Neutron Flux | |||
: l. Variable Overpower Trip 0 (2, 4}, M (3, 4) 1 2 C (4) | |||
: 2. Logarithmic Power, Level - High R. (4} M and S/U (1) 1, 2, 3, 4, 5 and " | |||
C. Core 1. | |||
2. | |||
Protection Calculator System CEA Calculators Core Protection Calculators D R ',R(6) | |||
(2, 4), R (4, 5) ';M (9) R (6) | |||
I 1,2 1, 2 ) | |||
M (B), S'(7) | |||
1 Oi | |||
TABLE.4.3-1 (Continued) | |||
REACTOR PR TECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS | |||
( | |||
Pl Kl Cl CHANNEL MODES IN MHICH foal CHANNEL CHANNEL FUNCTIONAL . SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE UIRED D. Supplementary Protection System Pressurizer Pressure - High 1, 2 II. RPS LOGIC 1 | |||
A; Matrix Logic N.A. N.A. 1, 2, 3", 4+, 5" | |||
: 8. Initiation Logic N.A. N.A. 3A 4* Pk III. RPS ACTUATION DEVICES I A. Reactor Trip Breakers N.A. N.A. M, R'-P9,0):; . 1, 2, 3", 4*j 5" B. Manual Trip N.A. N.A. M 1 2 3A 4A 5A | |||
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TABLE 4.3-1 | TABLE 4.3-1 Continued) | ||
TABLE NOTATIONS With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel. | |||
Each STARTUP or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if ro performed in the previous .7 days. | |||
(2) Heat balance only (CHANNEL FUNCTIONAL TEST not included), above 15K of RATED THERMAL POWER; adjust the linear power level, the CPC delta T power and CPC nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than 2X. During PHYSICS . | |||
TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau. | |||
TABLE NOTATIONS | (3) Above 15K of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators. | ||
Neutron detectors may be excluded from CHANNEL CALIBRATION. | Neutron detectors may be excluded from CHANNEL CALIBRATION. | ||
After each fuel loading and prior to exceeding 70K of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall use these elements. | |||
(6) This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the charm'el as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions. | |||
(7) Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is less than or equal to the actual flow rate. The flow measurement uncertainty may be included in the BERRl term in the CPC and is equal to or greater than 4X. | |||
(s) Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differentral pressure instrumentation and the ultrasonic flow meter adjusted pump curves or calorimetric calculations. | |||
thl CHANNEL FUNCTIONA vent>cation that~ (~(z t | |||
CPC per-Specification 2.2.2. | |||
. At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the .undervoltage and shunt trips. | |||
PALO VERDE " UNIT 1 3/4 3-X5 | |||
O~ | |||
0 il | |||
SMITCH DISCONNECT SMITCHES LOCATION SG 1 1-ine 2 Atmospheric Dump'dai~~ Qiovc o Alit v RSP Val ve~ SGB-HY-178A Ann SOS-H). nS R, | |||
: 2. SG 2 line 1 Atmospheric Dump Ua~QK 5>lbnlo'~n Alt | |||
TABLE 3.8-2 (Continued) | TABLE 3.8-2 (Continued) | ||
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY | CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY,DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER 'DESCRIPTION E-NAN-SOlM E-NAN-S01A RCP M-RCE-P01A (C.E. NO. 1A) | ||
E-NAN"S03B E-NAN-S01L E-NAN-S01A RCP M"RCE-Pole (C.E. NO. 2A) | |||
E-NAN"S03B E"NAN-502L E-NAN-S02A 'RCP M"RCE-P01B (C.E. NO. 1B) | |||
E-NAN-S04B X E-NAN-SO M f"NAN-S02A RCP M"RCE"P01D (C.E. NO. 2B) | |||
E-NAN-S04B E"NGN-L03C2 FUSE IN BKR. CTMT NOR DUCT HTR M-HCN"Eolc E-NGN"L03C3 FUSE. IN BKR. CTMT NOR DUCT HTR M-HCN-E01Q E-NGN-L03D2 FUSE IN BKR. CTMT POLAR CRANE M-ZCN-GOl E-NGN-L06C2 E-NGN-BOGC2 CTMT PRE-ACCESS NORM AFU FAN (FUSE) M-HCN-F01A E-NGN-L09C4 E-NGN-B09C4 CTMT PRE-ACCESS NORM AFU FAN (FUSE) M-HCN-F01B E-NGN- L10C2 FUSE IN BKR. 'CTMT NORM DUCT HTR M- HCN" E01A E-NGN- LlOC3 FUSE IN BKR. CTMT NORM DUCT HTR M-HCN" E01B f~ ggg e p( jQQQ I | |||
PROPORTIONAL HTR BANK M-RCE"B2, QFu.X B8 B14 | |||
- RH- ~stoa F-Q&,Q - QLZ.C.Q PROPORTIONAL HTR BANK M-RCE-B5, 7-U 'bZ. Bll, B17 CEA 06 CB101 F101, F102, F103 CEA 06 CEA 08 CB102 F104, F105,, F106 CEA 08 CEA 10 CB103 F107, F108, F109 CEA 10 PALO VERDE - 'UNIT 2 3/4 8-29 | |||
'CTMT NORM DUCT HTR M-HCN" E01A CTMT NORM DUCT HTR M-HCN" E01B PROPORTIONAL HTR BANK M-RCE"B2, B8 B14 PROPORTIONAL HTR BANK M-RCE-B5, Bll, B17 CEA 06 CB101 | |||
' | |||
II 0 | |||
~O | |||
CD)~1' | TABLE 3. 8-2 '(Continued)" | ||
'::-9 8" | CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION CEA 51 CB103 F107, F108, F109 . CEA 51 CEA 53 CB104 F110', Fill, F112 CEA 53 CEA 30 CB101 F101, F102, F103 CEA 30 CEA 31 CB102 F104, F105, F106 - CEA 31 CEA 32 CB103 F107, F108, F109 CEA 32 CEA 33 CB104 F110, Fill, F112 CEA 33 CEA 01 CB101 F101, F102, F103 CEA 01 E-PHA-D33-03 E-PHA-M3332 INDICATING LIGHTS FOR VLV J"SIA"UV"634 | ||
~ | |||
E-PHA-D33-04 E-PHA-M3332 INDICATING LIGHTS FOR VLV J"SIA-UV"644 E- P HB-D36-01 E"PHA-M3638 INDICATING LIGHTS FOR VLV '-SIB"UV"614 E"PHB-D36-02 E-PHA"M3638 INDICATING LIGHTS FOR VLV J-SIB-UV-624 E"NHN"D28-04 E-NHN-M2830 CONTAINMENT PREACCESS NORMAL AFU MOTOR SPACE HEATER FOR M"MCN-F01AH E"NHN-D28-14 E-NHN-M2830 'LOW SWITCH J"HCN"FSL-29 FOR DUCT HEATERS M"HCN-E01A AND B A<A E"NHN"028"16 E-NHN-M2830 CONTAINMENT AH5'UCT HEATERS M-HCN-EOlA AND B TEMPERATURE CONTROL J-HCN-TC-29 E"NHN"D28"18 E-NHN-M2830 'LOW SWITCH J"HCN-FSL"31 FOR DUCT HEATERS M-HCN-Eolc AND 0 E" NHN-D13-04 E" NHN"M1329 CONTAINMENT ACU DUCT HEATERS M-HCN-Eolc AND 0 TEMPERATURE CONTROLLER J-HCN"TC-31 PALO VERDE - UNIT 2 3/4 8"34 | |||
il~ | |||
li | |||
. TABLE 3'.8-2 (ContinLre@ | |||
CONTAINMENT PENETRATION KNPiJK'ffiaff OVERCURRENT PROTECTIVE I%K~ | |||
PRIMARY DEVICE BACKUP DEVICE SERVICIE NUMBER NUMBER DESCRIPTWN E-NHN-D13-22 E-NHN-.M1329 STEAM GEiEMh(IGRf N&il'ctQUP RBtttfP MOTE SPMK fHiWiEiR MI.88~KUIH E-NHN-D15-01 "-. E-NHN-M1526 REACTOR UQKNlfl BUMP.'%ÃSE MRCE HEAKiR FiBKMH&fMI RGKw7JXLB E-NHN-D15-02 E-NHN-M1526 'REACTOR HSluTii'UMP'%ME 5FAK HEATERf CM6%5RRf'rRQK-;BflTiiiBQ E-NHN-D15-06 E-NHN-M1526 FAN ~f CONTAINMBffll'ZKGGKGK'HGHIIINL N88 SBNCIE &K%% QKA~~'R M-Hcifti~'P'@XSAM ~ % | |||
'E-NHN-D10-01 E-NHN-M1027 REACTOR. CBV~Q'UMIP M03i'QRf, SNKZ | |||
'HEATEU Gi&Rr@HRHf Ql.RfLi-:HQZLNB E-NHN-D10-02 E-NHN"M1027 REACTOR Cmui. N1li W)PIP tNJTDff %MR HEATER ~FQkQQR hl 963-:H%EDI E-NHN-D10-20 E-NHN-M1027 STEAM GENBQgfM< %fEIl LiAV(8P 5M'RMRH<'~ifhKll!B3 HUNR'OTOR E-NHN-D19-05 E"NHN-M1914 CEDM NORMAl. AQS IiAh'I tel"82i KM% | |||
HEATER BI.IHltff.Nial E-NHN-D19-06 E-NHN-M1914 CEDM NORMAL NUN KMI;h$7i,RRf MME HEATER Qi. Pc(Uf HNK'rH E-NHN-D19-07 E-NHN-M1914 CONTAINMENT 0ERNLi. NiBj iRNI.MSIKfR SPACE llFNtlW tiff Ni&N2LNI E-NHN-D19"08 E-NHN-M1914 CONTAIN'IENT NSfHM'Q. 4EQJ llama iViSliXE | |||
.) a SPACE. HHKER ti~ftfff-.4%IlZHl E-NHN-D19-10 E-NHN-M1914 REACTOR .CAVITY MIRML XZEQ3M,FkM: | |||
~ 4 MOTOR SPRITZ HE2%KRf | |||
'e, M"HCN-AQ3NM C | |||
E-NHN-019"12 E" NHN-M1914 REACTOR CAVGV( HfafftlM CMIQNEI SPME I!EAWERf IF'OTOR M-HCN"AEKHI PALO VEROE - UNIT 2 3/4 8-35 | |||
Il TABLE 3.8-2 (Continued), | |||
CONTAINMENT PENETRATION CONDUC'HE OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-ZAB-C06 E-PKB-D2221 SAFETY INJ TAN( lbhK'!RGB'EI SURD.'7< VAlVE (FUSE) J-SIB-~622 Hv . | |||
E-ZAB-C06 E-PKB-D2221 SAFETY INJ TANK VLF Wl!%E (FusE) J-SIB-HV-613 E"ZAB"C06 E-PKB-D2221 SAFETY INJ TANK'/GNW VN!VK (FUSE) J"SIB"HV"623 E-ZAB"C06 E-PKB-D2221 SAFETY INJ TANK VHH'i3'NlVE: | |||
(FusE) J"SIB"HV-633 E-ZAB-C06 f-PKB-D2221 SAFETY INJ TANK VGi9% VMS (FusE) J-SIB-HV-643 E-ZJA"C01 E-PKA-D2101 SAFETY INJ TANK KGlRQZHHI NRPLV( ViÃVE (FUSE) J-SIA"HV-639 E-Z JA" C01 E-PKA-D2101 SAFETY INJ TANK MKGlRQEM SMBPlLV( VIVE (FUSE) J-SIA-HV-649 E-ZJA-C03 E- PKA-D2111 RCP CONTROLLED BllHDSBF 70 Rlott VihD'tE (FUSE) J-CHA-HV-507 E-ZJA"C03 E-PKA-D2111 LETDOWN LINE TG RGBKS'BE% EXCH!"L'.iM'SO VALVE (FusE) J" CHA"HV"516 E-ZJA-C03 E- PKA"D2111 RCP CONTROL'LED B'QiEBGEiF %l VKH %fA'LVE (FUSE) J"CHA"UV"506 E-Z JB-C01 E" PKB"D2201 SAFETY INJ TANK F311lL NM EMEN MLLE (FusE) J-SIB"UV-641 E-ZJB-C01 E" PKB" 02201 SI TANK CHECK VXflMK L!EK~ 299 VALVE (FusE) J-SIB-UV-648 E-ZJB-C01 ~ E-PKB-D2201 HOT LEG INJECT XHEKK VALI! IliMfNBE ISO VLV (FUSE) J-SIB" UV-322 E-ZJB-C01 E- P KB-02201 SAFETY INJ TANK NIHMGBH SERPENS VALVE (FUSE) J-SIB-Pf-632 Hv'ALO VERDE " UNIT 2 3/4 8-37 | |||
41 TABLE 3.8-2 (Continued) | |||
CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEYICES PRIMARY'EVICE BACKUP DEVICE SERVICE NUMBER 'NUMBER DESCRIPTION E-Z JB-COl E"PKB-D2201 'AFETY INJ TANK NITROGEN SUPPLY VALVE (FUSE) J-SIP-'8-"42 lj '-ZJB-C03 E" PKB-D2211 H4'ETDOWN LINE TO REGEN HEAT EXCH VALYE (FUSE) J" CHB"UV-515 E-ZJB-C03 E- PKB-02211 SAFETY INJ TANK FILL AND DRAIN VALVE (FUSE) J"SIB-UY-631 E-ZAA-C03 , E" PKA-D2109 REACTOR DRAIN TANK OUTLET ISOLATION VALVE (FusE) J-CH UV"560 E-ZAA-C03 E-PKA-02109 SI TANK RWT HDR CTMT ISOLATION VALYE (FUSE) J"SIA"UV-682 gV E-ZAA-C03 E-PKA-D2109 REGENERATIYE HEAT EXCH TO AUX SPRAY VALVE | |||
~@USE) J-CHA-HV-M 2oS E-ZAA-C01 , E-PKA-D2110 SAMPLE CONTAINMENT ISOLATION VALVE (FusE) J"SSA-UV-203 E"ZAA"C01 E- PKA-02110 SAMPLE CONTAINMENT ISOLATION VALVE (FUSE) J-SSA-UY-204 E -ZAA-C01 E-PKA-02110 SAMPLE CONTAINMENT ISOLATION YALVE (FUSE) J-SSA"UV"205 | |||
~~+ E-ZAA-C04 E" PKA"D2102 PRESSURIZER VENT VALVE | |||
~(FUSE) J" RCA-HY"103 Pn E"ZAA-C05 E-PKA-02114 STEAM GEN BLO'WDOWN CTMT ISOLATION VALVE (FusE) J"SGA-UV"500P | |||
~~ | |||
~f'-ZAA"C05 E-PKA"D2114 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGA-UV"204 E-ZAA"C05 E" PKA-D2114 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGA-UV-211 E-ZAA-C05 E-PKA-02114 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGA-UV-220 E-ZAA-C06 E- PKA-02121 SAFETY INJ TANK NITROGEN SUPPLY VALVE | |||
'FUSE) | |||
J-SIA-HY-619 PALO VERDE UNIT 2 3/4 8"38 | |||
Il il | |||
!I | |||
w~~r g m ~r, zp- e-~a. | |||
E- z,AA-cd ~-PKA.1oz>o> gE.ACToA CooL,Axrt 9 E,~T g~us< a- RcR-Hg-l~( | |||
Ipse,vw ~o pg z/+ s->a 6- 'RAP '-co% K-P~ ~><>G ~~ TR> QhAE.W'T PLDRQG pe~ ER | |||
( Fu.SGQ p ~e.ss M oDE, iso>.Av <~ | |||
vA~vc-. z-c.PR -Q V- 9A | |||
0 | |||
!I 0 | |||
TABLE 3.8-2 (Continued) | |||
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-ZAA-C06 E" PKA-D2121 SAFETY INJ TANK NITROGEN SUPPLY VALVE (FUSE) J" SIA-HV-629 E-ZAA-C06 E-PKA-02121 SAFETY INJ TANK VENT VAL'VE (FUSE) J-SIA-HV-605 E"ZAA-C06 E-. PKA-D2121 SAFETY INJ TANK 'VENT VALVE (FUSE) J"SIA-HV-606 E-ZAA-C06 E" P KA-02121 SAFETY INJ TANK VENT VALVE (FUSE). J" S IA-HV-607 E-ZAA"C06 E-PKA-D2121 SAFETY INJ TANK VENT VALVE (FUSE) J"SIA-HV-608 E"ZAA"C06 E" P KA-D2121 RC 'SYSTEM VENT TO CTMT VALVE (FUSE) J-RCA-HV"106 E-ZAB-C03 E"PKB"D2209 REGEN HEAT EXCH TO AUX SPRAY VALVE (FUSE) J-CHB-HV-203 E"ZAB-C03 E-PKB"02209 REACTOR COOLANT VENT VAL'VE (FusE) J- RCB" HV-102 E-ZAB-C03 f-PKB-02209 SAFETY INJ: TANK FILL AND DRAIN VAlVE (FUSE) J-S I B-UV-611 E-ZAB-C03 E"PKB"D2209 SI TANK CHECK VALVE LEAKAGE LINE ISO VALVE (FusE) J-S I 8-UV-618 E-ZAB"C01 E- P KB-D2210 CTMT ATM RADIATION MONITORING ISO VALVE (FusE) J-HCB-UV-44 E"ZAB-C01 E-PKB-D2210 CTMT ATM RADIATION MONITORING ISO VALVE (FusE) J-HCB-UV-47 E-ZAB-C04 E-PKB"D2202 REACTOR COOLANT VENT VALVE (FUSE) J- RCB-HV-108 E"ZAB-C04 E-PKB-D2202 SAFETY INJ TANK FILL AND DRAIN VALVE (FUSE) J-SIB-UV-621 E-ZAB-C04 E-PKB-D2202 SI TANK CHECK VALVE LEAKAGE LINE ISO VALVE (FUSE) J-SIB-UV-628 p '4AQ C<h R- pKS-ORE>>. Qbk)TA114%4l4T Qci4ha f4 94hCC 4 | |||
+04 ~~>ivy, VAav~ g CPS PALO VERDE - UNIT 2 3/4'-39 | |||
0 I | |||
0 | |||
TABLE 3.8-2 '('Continued) | |||
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-ZAB-C05 E-PKB-D2214 REACTOR COOLANT VENT VALVE (FUSE) J" RCB-HV"109 E-ZAB-C05 .. E-PKB"D2214 STEAM GEN BLOWDOWN CTMT ISOLATION VALVE (FUSE) J-SGB-UV-500R E-ZAB-C05 E-PKB" 02214 BLOWOOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J"SGB-UV"222 E-ZAB-C05 E-PKB" D2214 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J"SGB-UV-224 E-ZAB-C05 E- PKB-02214 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGB-UV-226 E-ZAB-C06 E-PKB-D2221 REACTOR COOLANT VENT VALVE (FUSE) J-RCB" HV"105 E-ZAB-C06 E-PKB-D2221 SAFETY INJ TANK NITROGEN SUPPI Y VALVE (FUSE) J-SIB-UV-612 E-ZJB-C03 E-PKB-02211 SI TANK CHECK VLV LEAKAGE LINE ISO VALVE J-SIB"UV-638 (FUSE)'"ZJB"C03 E" PKB" D2211 HOT LEG INJECT CHECK VLV .LEAKAGE ISO VLV (FUSE) J-SIB-UV-332 E-ZAN-COl E-NKN-D4226 SEAL INJECT VALVES TO RCP (FUSE) J-CHE" F V-241 E-ZAN-COl E-NKN-D4224 SEAL INJECT VALVES TO RCP (FUSE) J-CHE-FV-242 E-ZAN"C01 E"NKN-D4222 SEAL INJECT VALVES TO RCP (FUSE) J-CHE-FV-244 E-ZAN-COl E"NKN-D4224 POST ACDT SMPLG SYS ISO VALVE (FUSE) J-CHN-HV-923 E-ZAN-C01 E"NKN-D4224 REACTOR VESSEL SEAL DRAIN TO RDT VALVE (FUSE) J-RCE-HV-403 E" E-NKN-04224 SI DRAIN TO REACTOR DRAIN TANK VALVE ZAN-C01'FUSE) | |||
J-SI E-HV-661 PALO VERDE - UNIT 2 3/4 8-40 | |||
II TABLE 3.8-3 MOTOR"OPERATED VALVES THERMAL OVERLSQS PROTECTION AND/OR BYPASS DEVICES BYPASS Ui:VICE sfslim(,$ 3 YALYE NUMBER Accident Conditions MFKGt28 J-SIA-UV-647 HPSI A Flow Control to Sx&@p 3hgert~en Reactor Coolant Yalve StQIHG&nl Dg. 5+5. | |||
'-SIA-UY-637 HPSI A Flow Control to Rc&'bp K~WiJc)n Reactor Coolant Valve %u5dbwm EH@ 5ys. | |||
J-SIA-HV-604 HPSI Pump A Long Term 5afiaCp Rgactann Cooling Valve RukMdh'nl K3g 5+s. | |||
J-SIB-HV-609 HPSI Pump B Long Term SRCL~/ ZAQBUflion Cooling Valve %u55lnvm 6",ilg. Sys. | |||
J-SIA-HV-657 Shutdown Clg. Temp. SMMivg EiqjjaMiea Control Train A Valve WuWtuvm C:ilg. Sys. | |||
J-SI 8-HV-658 Shutdown Cl g. Temp. Ra@My Kvg~mt$ eni Control Train B Valve Nu68b%01 K tlat, S+s J-SIA-HV-685 LPSI - Ctmt Spray Pump SRCh> VnjjeW$exa Cross Connect A Valve Sdu5dbmn> Cifg., $>ys J" SIB"HV-694 LPSI- Ctmt Spray Pump 9MhNp IInjj~>en Cross Connect B Valve %L'tiltbvNl C,ltd., Syz J-SIA-HV-686 Ctmt Spray A Cross 9897aM+ ~~g~g<QQ Connect Valve %Mnltavm Z1ig Sys. | |||
J" SIB-HV-696 Ctmt Spray B Cross SM~ Kzgertaon Connect Valve %uMwm (C~Ig. +ys. | |||
J"SIA"HV-688 .Shutdown Clg. Heat Kagact~un Exchange A Bypass Valve XtaC~Cm<a <i;lghays. | |||
J-SIB" HV"693 Shutdown Clg. Heat ~Wg Ztqjacttien Exchange B Bypass Yalve &uCcthurn King hays. | |||
J-SIA-UV-617 HPSI A Flow Control To Ka~y Zagecta on React Coolant 2A Yalve 9Bv@a5nvm Cltg Sys. | |||
PALO VERDE - UNIT 2 3/4 8-43 | |||
0 is | |||
TABLE 3.S-3 $Ga~ixue~ | |||
MOTOR-OPERATED VALVES TFKRAM'. SSRRBD@9 PROTECTION AND/OE( EVPkSS ZEGEi BYPASS DEVICE s)7GwBK53 YALVE NUMBER Accident Condiikweae, AKFECTi,ED J-SI A"UV-627 HPSI A Flow Cori&all Te 5zi5edp Eqgecti on React Coolant '2B Vivre 'ShI.@thorn Clg.,Sys. | |||
J-SIA-UV-645 LPSI F,low Contrail Te React Coolant O'R ~3Italiva | |||
~i'~ Zmgacti S5uiMavm on Clg. Sys. | |||
J-SIA-UV-635 LPSI Flow Conteeti ifh 'SiaeTa4y ejecta on React Cool ant 'l% '>Jallvm SNv@eimvm C3~g. Sys. | |||
J-SIA-UV-644 Safety Injecthm 1~k 3$ SaiTxtipj ejection Isolation, Valve SMuNehwn Zlg.'ys. | |||
J-SIA-UV-634 Safety Injectiera Thnk 3k SzNWy i~sgecti on Isolation Valve SMu5zhen. Llg. Sys. | |||
J" S I B-UV.-616 HPSI B Flow CoxOmli Te "'AM@ Zrgecti on React Cool ant 2k '4~allcm Slud'ibsen> ZOg, Sys. | |||
J"SIB-UV"626 HPSI B Flow CorCm~ll ite GRAM+ ZKQecti on React, Coolant 29 0'alum $ )Mc5uve Clig. Sys.. | |||
J;SIB-UV"'36 HPSI, B F3ow Cmtrell Ye SMxlgi Zejecti on React Coolant 3k '3htzl(ve'. SWtMuve 'C39.. Sys. | |||
J"SIB"UV"646 HPSI B Flow Cmfuuli <te 9hcTe~~ Znjecti on React Coolant 3$ %hfl'm SlbM~a iCOg. Sys. | |||
J-SIA"UV"655 Shutdown .Clg. M~ Sa>SM~y Zxgecti.on Isolation Loop 2 @alive~ Shura ~Clg. Sys. | |||
J-SIB-UV"656 Shutdown Clg. ZXW Mf~p Zegection Isolation Loop 2 'EMwa Shu~wil Clg. Sys. | |||
J-SIA-UV"664 Ctmt Spray Pump 4 Refueling Mater Tank itIo ~ Rejection SbuMnwn Cl g. Sys. | |||
~0 Isolation Vlv. | |||
' 1 n | |||
PALO VERDE - UNIT 2 | |||
4I 0 | |||
TABLE 3.8-3 (Continued) | |||
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSTEM(S) | |||
VALVE NUMBER Accident Conditions) AFFECTED J-SIB-UY"665 Ctmt Spray Pump B Injection | |||
'afety To Refueling Water Tank Shutdown Clg. Sys. | |||
Isolation Vlv. | |||
J-SIB-UY-615 LPSI Flow Control To Safety Injection React Coolant 2A Valve Shutdown Clg. Sys. | |||
J"SIB"UV"625 LPSI B Flow Control To Safety Injection React Coolant 2B Valve Shutdown Clg. Sys. | |||
J-SIA-UV-666 HPSI .Pump A to Refueling Safety Injection Mater Tank Isolation Shutdown Clg. Sys. | |||
J-SIB-UV-667 HPSI Pump B to Refueling Safety Injection Mater Tank IsoIation Shutdown Clg. Sys. | |||
J" SIA-UV-669 LPSI Pump A To Refueling Safety Injection Mater Tank Isolation Shutdown Clg. Sys. | |||
J-SIB-UY-668 LPSI Pump B, to Refueling Safety Injection Mater Tank Isolation Shutdown Clg. Sys. | |||
J-SIA-UY-672 Ctmt Spray Control Train A Safety Injection Yalve Shutdown Clg. Sys. | |||
J-SIB-UY"671 Ctmt Spray Control Train B Safety Injection Yalve Shutdown Clg. Sys. | |||
J-SIA-UY-674 Ctmt Sump Isolation Safety Injection | |||
'.; Train A Valve Shutdown Clg. Sys. | |||
bl J-SIB"UY-676 .'Ctmt Sump Isolation Safety Ingectson Train B Yalve Shutdown Cl g. Sys. | |||
J"SIA"UY"651 Sh'utdown Cl g. Isol ati on Safety Injection Loop 1 Yalve Shutdown Clg. Sys. | |||
J-SIB"UY"652 Shutdown Clg. Isolation Safety Injection Loop 2 Yalve Shutdown Clg. Sys. | |||
PALO VERDE - UNIT 2 3/4 8-45 | |||
0 0 | |||
TABLE 3. 8-3,(Conti nued) | |||
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSTEM(S) | |||
VALVE NUMBER Accident Conditions AFFECTED J-SIA-UV-673 Ctmt Sump Isolation Safety Injection Train A Valve Shutdown Clg. Sys. | |||
J-SIB" UV-675 Ctmt Sump Isolation Safety Injection Train B Valve Shutdown Clg. Sys. | |||
J-SIB-UV-614 Safety Injection Tank 2A Safety Injection Isolation Valve Shutdown Clg. Sys. | |||
J"SIB-UV-624 Safety Injection Tank 2B Safety Injection Isolation Valve Shutdown Clg. Sys. | |||
J-S IA-HV"684 Shutdown Clg. Heat Safety Injection Exchange Isolation Train A Shutdown Clg. Sys. | |||
J-SIB-HV-689 Shutdown Clg. Heat -Safety Injection Exchange Isolation Train 'B Shutdown Clg.. Sys. | |||
J-SIA-HV-683 LPSI Pump A Isolation Safety Injection-Val ve Shutdown Clg. Sys. | |||
J"SIB-HV"692 LPSI Pump B Iso'lation Safety Injection Valve Shutdown Clg. Sys. | |||
J" SIA-HV-691 Shutdown Clg. Loop 2 Safety Injection Warm-Up Bypass Valve .Shutdown Clg. Sys. | |||
J"SIB-HV"'690 Shutdown Clg. Loop 1 Safety Injection Warm-Up Bypass Valve Shutdown Clg. Sys. | |||
J"SIA-HV"698 HPSI Pump A Discharge Safety Injection Valve Shutdown Clg. Sys. | |||
J" SIB-HV"699 HPSI Pump B Discharge Safety Ingectson Valve Shutdown Clg. Sys. | |||
J-SIA-HV"306 LPSI Pump A Header Safety Injection Discharge Valve Shutdown Clg. Sys. | |||
PALO VERDE " UNIT 2 3/4 8"46 | |||
0 il | |||
TABLE 3.8-3 (Continued) | |||
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSTEM(S) | |||
VALVE NUYiBER Accident Conditions) AFFECTED J-SIB-HV-307 LPSI Pump B Header Safety Injection Discharge Valve Shutdown Clg. Sys. | |||
J-SIA-HV-687 Ctmt Spray Isolation Train A Safety Injection Valve Shutdown Clg. Sys. | |||
J-SIB-HV-695 Ctmt Spray Isolation Train B Safety Injection Valve Shutdown Clg. Sys. | |||
J-SIA-HV-678 Shutdown Clg. Heat Exchange Safety Injection Isolation Train A Shutdown Clg.'Sys. | |||
J-SIB-HV-679 Shutdown Clg. Heat Exchange Safety Injection Isolation Train B Shutdown Clg. Sys. | |||
J-SIC-UV-653 Shutdown Clg. Isolation Valve Safety Injection Shutdown Clg. Sys. | |||
J-SID" UV-654 Shutdown Clg. Isolation Valve Safety Inject'ion Clg. Sys. 'hutdown J-EMA-UV-65 ECM Loop A To/Fi om NCM Cross Essential Cooling Tie Valve Mater System J- EMA-UV-145 ECM Loop A To/From NCM Cross Essential Cooling Tie Valve Mater System J- CTA-HV-1 Condensate Tank to Aux. Condensate Transfer Feedwater Pump Valve 8 Storage Sys. | |||
J-CTA-HV-4 Condensate Tank to Aux. Condensate Transfer Feedwater Pump Valve 6 Storage Sys. | |||
J-SGA-UV-134 SG-1 Aux. Feedwater Pump A Main Steam System Steam Supply J-SGA-UV"138 SG-2 Aux. Feedwater Pump A Main Steam System Steam Supply PALO VERDE - UNIT 2 3/4 8"47 | |||
II 0 | |||
TABLE 3.8-3 (Continued) | |||
MOTOR"OPERATEQ VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSYEH(S) | |||
VALVE NUMBER Accident Conditions AFFECTED J"NCB-UV-401 NCMS Ctmt Isolation Valve Nuclear Cooling Mater System J-NCA-UV-402 NCMS Ctmt Isolation Valve Nuclear Cooling Mater System J-NCB-UV-403 NCMS,Ctmt Isolation Yalve Nuclear Cooling Mater System i J-AFB-HV-30 Aux. Feedwater Regulating Auxiliary Feed-Valve water System ' | |||
J"AFB-HV-31 Aux. Feedwater Regulating Auxi1 iary Feed-Valve water System J-AFB-UY-34 Aux. Feedwater Regulating "Auxiliary Feed-Yalve water System J-AFB-UV-35 Aux. Feedwater Regulating Auxiliary Feed-Valve water System J"AFA-HY"32 Aux. Feedwater Regulating Auxiliary Feed-Val ve water System J-AFA-UV-37 Aux. Feedwater Isolation Auxiliary Feed-Val ve water System J"AFC-UV-36 Aux. Feedwater Isolation Auxiliary Feed; Yal ve water System J-AFC-HV"33 Aux. Feedwater Regulating Auxiliary Feed-Valve water System J-CPA-UV-2A Ctmt Purge Refueling Mode Containment Purge Isolation Valve System J-CPB-UV-3B Ctmt Purge Refueling Mode Containment Purge Isolation Valve System J-CPA"UV-2B Ctmt Purge Refueling Node Containment Purge Isolation Valve System PALO YERDE - UNIT 2 3/4 8-48 | |||
4$ ~ | |||
il 0 | |||
TABLE 3.8-3 $C~zatm8) | |||
MOTOR-OPERATED VALVE ~iOKL SWiBHIIDMl PROTECTION AND/OR 3FPMS EEKKKS BYPASS DEVI'CE Sifts"iKMQS]} | |||
VALVE NUMBER Acci dent Cendif%cea NFRHKTiiiB J"CPB"UV"3A Ctmt .Purge RefceTIfng ItIhM (Uanthmznnexft, Purge Isolation Valve SpMKHA J-MCA-UV-62 Normal Chill M~Nm Rhtfzen. Gati ITIT!+6 '~Rater Ctmt Isolation Spr@znn J"MCB"UV-63 Normal Chill 'M~>>, %pg>TQ~ CthÃnlt+5 ')Mes Ctmt Isolatien Spf$ 5'ellA | |||
'J-MCB-UV-61 Normal Chal Wa5ar FNlmw GNii'iITIa4 %L~~r Ctmt Isolation Sy~ | |||
J-ROA-UV-23 Ctmt Radwas& Rmgxs K>CmnaBI Rhdlii~$vre Maste Isolation 9%89llll 5~10 J-HPA-UV-3 H2 Ctmt Train A RnvaWmsrm Smdztiimmm<~'ydrogen Supply Isolation CaMareil Sygs J"HPA"UV-5 H2 Ctmt Train A R'~me Gbn5zriizmmdt Pr4rogen Isolation Valve FezrWe)TI Syr, J"HPB"UV-4 H2 Ctmt Traaa 3 Hhe~eeam> GhnNzNrnmanII: Rgdrogen | |||
,Supply Isolation Gmvbr+TI S~., | |||
J-HPB-UV-6 H2 Ctmt Train B Rhyme GhllCK181~, 39@drogen Isolation Valve E'eaCnuN 5gps J-HPB-UV-2 H2 Ctmt Train B U~tmem Emdmmment Bydrogen Supply Isolation Eam&eil Sgs. | |||
J-HPA-UV-1 H2 Ctmt Train A SIM~naam EB'JCMXIDBllj, hydrogen Supply Isolation EmkamTI Sys. | |||
J"GRA-UV-1 Radioactive Draira Zk: Gas (kheamm Radwaste Surge Hdr Internal ZunM5mmC ~Q'tRfm Isolation PALO VERDE - UNIT 2 3/4 8-49 | |||
0 Ib 0 | |||
3/4. 9 REFUELING OPERATIONS 3/4. 9. 1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 'Mi h.+he reactor vessel head closure boits less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is. met: | |||
: a. Either a K ff of eff 0.95 or less, or | |||
: b. A boron concentration of greater than or equal to 2150 ppm. | |||
APPLICABILITY: MODE 6+. | |||
ACTION: | |||
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity chagges and initiate and continue boration at greater than or equal to Z4o~gpm of a solution containing > 4000 ppm boron or its equivalent until K ~ is reduced to less than or equal to 0.95 or the boron concentration is r5ftored to'greater than or equal to 2150 ppm, whichever is the more restrictive. | |||
SURVEILLANCE RE UIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined, prior to: | |||
a~ Removing or unbolting the reactor vessel head, and | |||
: b. Withdrawal of any full-length CEA in excess of. 3 feet from its,fu!:y inserted position within the reactor pressure vessel. | |||
4.9. 1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be'determined by chemical analysis at least once per 72 hours. | |||
The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure. bolts less than fully tensione or with the head removed.. | |||
PALO VERDE - UNIT 2 3/4 9-1 | |||
ji il 0 | |||
3/4.10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for mea urement of CEA worth and shutdown ma g n !3 Qvided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s), or'he reactor is subcritical by at least the reactivity equivalent of the highest CEA worth. | |||
APPLICABILITY: MODES 2, 3" and 4"¹. | |||
ACTION: | |||
: a. With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi- | |||
,,...ately initiate and continue boration at greater than or equal to | |||
;~;S&~gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by. | |||
Specification 3.1.1.1 is restored. | |||
: b. With all full-length CEAs fully inserted and the reactor subcritical by less than he above reactivity equivalent, immediately initiate and continue boration at greater than or equal t&f& gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.l.l.l is restored. | |||
SURVEILLANCE RE UIREMENTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdr awn shall be determined at least once per 2 hour s. | |||
4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50K withdrawn. position within 24 hours prior to reducing the. SHUTDOWN MARGIN to less than the limits of Specification 3.1.l.l. | |||
4.10.1.3 When in MODE 3 or MODE 4, the reactor shall be determined to be subcritical by at least the reactivity equivalent of the highest estimated CEA worth or the reactivity equivalent of the highest estimated CEA worth is. avail-. | |||
able for trip insertion from OPERABLE CEAs at least once per 2 hours by con-sideration of at least the following factors: | |||
: a. Reactor Coolant System boron concentration, | |||
: b. CEA position, | |||
: c. Reactor Coolant System average temperature, | |||
: d. Fuel burnup based on gross thermal energy generation, | |||
: e. Xenon concentration, and | |||
: f. Samarium concentration. | |||
Operation in MODE 3 and MODE 4 shall be limited to 6 consecutive hours. | |||
Limited to low power PHYSICS TESTING at 'the 320'F plateau. | |||
PALO VERDE - UNIT 2 3/4 10-1' | |||
, ~ | |||
Ib 0 | |||
FIGURE 3.1 1 | |||
~ | |||
ALLOWABLEMTC MODES 1 AND 2 m PALO VERDE UNIT/CYCLE 1 C) m | |||
+1.0 I | |||
I Is I I | |||
I ~ I | |||
~ ~ << ~ ~' | |||
Q 40.5 l': ):I | |||
~ ~, I | |||
~ | |||
40.22 x | |||
~ | |||
jI II I Cl 1 hp/ | |||
'F , 0.0 hp /OF ) | |||
~ << | |||
I 4 0.22 (595 ~ ~ | |||
K ~ | |||
I I- 0 z | |||
uJ I | |||
(0 U | |||
u llJ 0u u) 0 | |||
-1.0 U) ALLOWA L MTC K | |||
.D I- cO z | |||
LU | |||
-2.0 I-0 I-K O ~ | |||
3.0 TG TH 0 AVG 2 I~ | |||
'i << | |||
) iI '.t; I~ I. | |||
,'I:,I i | |||
(596 F;3.5 x 10'46p/ Fj 48o'oo'500 | |||
~ << | |||
)I l!'~'' | |||
<< ~ | |||
' ~'ll li:. l | |||
~ | |||
~ | |||
4.0 coo' AVERAGE MODERATOR TEMPERATURE, F | |||
II i/ | |||
0 | |||
136'.6" (40K) 135'-6" (30K) 135'-10"'(33 5K) ~ | |||
( | |||
"134'-6" (20K) | |||
..:133'-3" (7.25K).- | |||
133'-6" (10K) | |||
COLD S/D VOLUME 0 | |||
0 200 400 600 AVERAGE REACTOR COOLANT SYSTEM TEMP F 80)io 600 ,000 GAL. (565 F) 600 575K 75/o 573 744 G 4L (1200 F) 55nK MINIMIJniI USEFUL COLD S/D VOL. PLUS VOLUME (1) 70/o MARGIN IEQUI RED IN THE RWT RWT 5nnK LEVEL'NSTRUMENT READING (1) 65% | |||
475K ESF VOL. PLUS MARGIN (3) 01'2) OK 200 400 609 AVERAGE RCS TEMPERATURE, F (1) THE TANK LEVEL AND VOLUMC SHQSVN ARE THE USEFUL LEVEL AND VOLUME ABOVE THAT IN THE TANK "YHICH IS REQUIRED FOR VORTEX CQNSIDERATIONS (2) DURING MODE 5 AND 6 ONE OF THESE BORATED SOURCES SHALL CONTAIN A MINIMUMOF 33,NO GALLONS (3) THIS VOLUME'IS NOT REQUIRED DURING MQPE 6 F IGUR E 3.1.2 MINIMUMBQRATED lVATER VOLUMES PALO VERGE - UNIT Q 3/4 1" 12 | |||
O~ | |||
O~ | |||
!5 | |||
FIGUR E 3.1-2A PART LENGTH CEA INSERTION LIMITvs THERMAL POWER 1.00 112.5" 0.90 0.80 ACCEPTABLE 0.70 OPERATION UNACCEPTABLE OP E RATION 0.60 0 0.50 50% POWER LINE INSERTION LIMIT 0.40 Z | |||
0.30 u | |||
0.20 0.10 22.5" 0.00 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 PART LENGTH CEA POSITION, INCHES WITHDRAWN | |||
~ i ll~ | |||
C7 1.00 m | |||
M A~ | |||
0.90 0.80 M VI I tn W~ | |||
0.70 -MQg 0 al) | |||
C/l R 0.60 C m O X7 ~M 41 C) C) 0.50 Ag MO f en% A TRANSIENT NSE ION LIi<IT 4P lA Vl I M 0.40 W f gJ f90 I | |||
Z Cll ~4 lA CA g 0) m 0. 30 J +~ fR. | |||
( ln M | |||
I 4J | |||
$ MW Ill Q.ZO 0:10 QidO | |||
'5U i50 30 f~O :!0 0 )50 !~C ~0 60 gg 0 | |||
/BE QXV+~UPf. = Qgggg | |||
~ | |||
il 0 | |||
FIGURE 3.2-1 DNBR MARGIN OPERATING LIMITBASEDOIQlmi.SR (COLSS IN. SERVICE) 100 K | |||
REGION OF 0 ACCEPTABLE | |||
" 'I- OPERATION | |||
~ | |||
80 U | |||
Z } | |||
~ | |||
0 I- LQ m C CL 0 g. | |||
CC 0 I- | |||
<.o R EGIN!(DH: | |||
Lfl 40 UNA"II:ZPHAGC~E LU 0 OP ERNKHISNJ O | |||
Ch | |||
'0 Z 0 oZ0 C5 0 | |||
0 20 40 60 8m PERCENT OF, RATED THERMALMilSER | |||
~ F,IGURE 3. 2-1 PNBR, MARGIN OPERATING 'LIMIT BASEP:ON UMSK (COL'SS IN SERVICE) | |||
.PALO'ERGE - 'UNIT& 3/4 2-6 | |||
ik~ | |||
il | |||
FIGURE 3.2-2 DNBR MARGIN OPERATING LIMITBASED ON CORE PROTECTION CALCULATOR (COLSS OUT OF SERVICE) 0.60 | |||
~ ~ ~ ~ ~ | |||
I ~ | |||
t ~ I i ~ ~ ~ v ~ ~ i | |||
~ ~ ~ ~ ~ | |||
: REGION OF ACCEPTABLE ~ ~ ~ | |||
0.55 OPERATION ~ ~ | |||
'I ~ | |||
~ ~ ~ ~ | |||
~ I l | |||
~ | |||
- ~ | |||
~ | |||
I ~ | |||
-.05, 0.51) . 'l.......'(.25, 0.51) | |||
I 0.50 I | |||
~ ~ ~ j | |||
''' I I ~ | |||
Q .....I... | |||
K ~ ~ - I I | |||
a | |||
~ I I' | |||
~ ~ | |||
- ~ ~ ~ | |||
I ~ ~ ~ ~ I I | |||
a ~ . )...~ (.30, 0.46) | |||
Cl g 045 | |||
'D :i: .REGION OF I . | |||
z :OPERATION;::: . | |||
-I 0.40 | |||
""I' -+ | |||
'( -.30, 0. 3S):- >'-:: .: ~ ~ | |||
~ ~ ~ ~ ~ ~ ~ ~ ~ | |||
0.35 0.30 | |||
-0.3 -0.2 -0.1 0.0 0,1 0.2 0.3 CORE AVERAGE ASI SEE SECTION 3.2.7 FOR THE ASI OPERATING LIMITS fIGURE 3.2-2 PNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS 5'COLSS OUT Of SERVICE) | |||
PALO VERDE - UNIT 3/4 2-7 | |||
i i | |||
0 | |||
FIGURE 3.2-3 REACTOR COOLANT COLD LEG TEMPERATURE vs CORE POWER LEVEL 580 575 570 | |||
: u. 570 O 568 568 565 AREA OF ACCEPTABLE cx 560 OP E RATION 562 g 555 Q | |||
552 O 550 8 | |||
l0 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL,% OF RATED THERMAL POWER FIGURE 3. 2-3 | |||
~~ | |||
REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POMER LEVEL PALO VERDE UNIT 2r 3/4 2-10 | |||
ib | |||
'FIG UR E 3.3-1 DNBR MARGIN'OPERATING LIMITBASED ON COLSS FOR BOTH CEAC'S INOPERABLE 140 | |||
~ ~ | |||
C< ~ | |||
7' | |||
~ \ ~ ~ ~ | |||
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ | |||
I i ~ ~ g I ~ ~ ~ | |||
I~ | |||
120 I ': ~ s (100, 118. 7) | |||
(, | |||
~ | |||
I | |||
~ ~ | |||
lX ~ ~ ~ .:. I95 I 112.7 ) | |||
~ ~ 4 | |||
~::":.:-.':-. | |||
za z i ~ ~ ~ ~ e | |||
~ 9 g ~ ~ ~ ~ ~ ~ | |||
~ ~ ~ | |||
100 *I Q Cu | |||
~ ~ | |||
CD :: ~ j- REGION OF ~ ~ | |||
e~ ~ | |||
ACCEPTABLE: ~ > | |||
i'".'::'. OPERATION i | |||
~ ' ~ ' I 79.4, 79.4) ." | |||
CC i- t m \~ | |||
~ p | |||
~ | |||
cL'L | |||
~ i ~ ~ ~ | |||
I | |||
~ ~ | |||
60 LCJ | |||
~ I 0Bz | |||
~o gg I | |||
LLI | |||
~ I CC | |||
'0K UJ Q | |||
I ~ | |||
REGION OF 40 UNACCEPTABLE-OP E RATION 0o 20 | |||
~ | |||
0 20 40 60 80 100 PERCENT OF RATED THERMAL POWER PALO VERGE - UNIT E 3/4 3-10 | |||
II 0 | |||
0 | |||
~ s ~ ~ ~ ~ s 1 | |||
~ | |||
s | |||
', s I I 1 I I I e' s s E s ~ I ( I I ! I t s s I ' i i s I ~ 1 ! I I I I o 250 ~ | |||
s e | |||
I: | |||
~ | |||
a ~ | |||
( ', e | |||
~ '1 ( | |||
I I I s I I I | |||
I | |||
~ | |||
( s, i s ( I I | |||
s e | |||
I | |||
~ | |||
I I | |||
I I | |||
i I | |||
s s | |||
I I | |||
I I | |||
s | |||
( | |||
I 1 | |||
j e | |||
I | |||
~ | |||
I i | |||
~ | |||
I I | |||
I I I! | |||
I s ~ ( I I ~ I I I I s I I I I ( j j s s I | |||
I ~ s ~ s ~ | |||
'e | |||
, s I' ! I I I | |||
~ | |||
I | |||
(; | |||
~ | |||
s s ~ e s s s | |||
' s i I I j s s e s ~ s I I 200 o e ~ | |||
'UNACCEPTABLE s | |||
s ~ I s ~ ! ! OPERATlON ~ ( s o | |||
s s ~ ~ I s ( ( I ( I ~ I I a | |||
~ ~; ! ~ | |||
~ s ( ~ I I I ( i s s s s ( | |||
s ' i I e | |||
I ~ ~ ~ S | |||
~ ~ I e s j s I i e s ~ | |||
+ 1SO | |||
~ I ~ ~ | |||
I | |||
~ | |||
s ~ | |||
s ~ I | |||
~ | |||
I s | |||
s | |||
~ | |||
~ | |||
~ ~, ~ ~ | |||
e | |||
~ | |||
I s | |||
( | |||
'. I i I: ! I | |||
'sI s% | |||
~ | |||
~ s ~ a ~ e s ! | |||
s s I I I ~ ( I e I i I . I | |||
~ ~ ( ( ~ 1 ~ ( I I ~ I '. ( I s I I ' | |||
O I ( I 1 I e e s I I ~ ! I I I ~ | |||
! I i ~ I I I I I I i I ! i | |||
'~ | |||
s ~ ~ ~ | |||
s I ! I ( ! I 1 I I I I I ' I I s I i I e I I ! I ' I ! 'i I I | |||
I I ! | |||
'II s | |||
CC ~ ~ | |||
( ( s I ~ 1 ( ~ | |||
i s ( ' I i.l I ' i s | |||
( i ~ ~ | |||
! i I I I I I I I I I i ~ ~ ~ I I 100 j s I a | |||
( s I I I I I I I i I ~ | |||
lX ~ | |||
I s s ~ s I I I' s | |||
I I I I | |||
~ ~ | |||
( s s I 1 I I s | |||
( ~ 1 ~ ( ~ I ( s ( s ~ ~ ~ ~ ~ | |||
I ! | |||
I I I ! I I I i I I, | |||
s ~ s | |||
~ s s ( ~ | |||
s I s I ~ s a I i i I I I i I I ( ~ i I I I ( s i t I i e s s I ~ | |||
I . ! | |||
t- a 1 I i I s I I z ACCEPTAB LE s I I ~ I ( | |||
I t | |||
I i | |||
I i I a s s | |||
s ~ | |||
~ ~ , OPERATlON I ( I ~ I I I I I s i ~ I e ! I s s GO I ~ I I I s I e I ' I I I I s ( ~ I s 0 s I s s i ' I ' I ! I s ! I I I I ~ s ~ | |||
'D a (;; I s I ~ | |||
~ ~ s ~ ~ | |||
~ | |||
s s | |||
I I (; s I I, s s ~ | |||
s | |||
~ | |||
~ 'I | |||
~ | |||
I 1 | |||
I ( | |||
e I I: 'I . | |||
I I S ~ | |||
I I | |||
~ | |||
I I | |||
I s | |||
i | |||
~ | |||
~ | |||
s I ~ . I | |||
~ | |||
~ | |||
I I | |||
~ ~ | |||
I I | |||
I I | |||
I O e ~ ~ I | |||
( | |||
I ~ s j I I | |||
s I | |||
~ e s s I I i: | |||
I ~ | |||
i I I I I I I | |||
~ '( | |||
I a (' ( I I I I s | |||
~ | |||
I | |||
~ | |||
I I I ~ s e ( ( | |||
30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE E UIVALENT I-131 .PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POMER MITH THE PRIMARY COOLANT SPECIFIC ACTIVITY > 1.0 Ci/GRAM DOSE E UIVALENT I-131 PALO VERQE - UNIT iree'/4 4-28 | |||
0 F I G URK 2 44 RCS P R ESS/TEMP ILBNPJS 0-19 VBR. | |||
3000 2500 | |||
~ I ~ yy | |||
~ | |||
~ ! | |||
ff t ~ | |||
~ ~ ~ l li | |||
~I * | |||
~l }U | |||
- wt' | |||
<<C l | |||
* VA ~~ | |||
,u) 2000 I~ | |||
Q~ | |||
~ ~ ~ ~ | |||
CC D C))ot-t ~ ! | |||
~ | |||
~ i.. | |||
-CC t~ l ~ | |||
W Ci l ~ 'I I | |||
1500 :. (1) 0 ="-.. ~ - ~ | |||
2) | |||
O ~ ~ ~ | |||
a ~~ | |||
' ~ | |||
z II | |||
't | |||
\~ | |||
~ ~ 'i | |||
~ ~ | |||
1000 | |||
". ~ | |||
. (3) ~ | |||
(5) 500 (4) 20 o/HR | |||
.. HEATUP | |||
: 5 100/HR COO LDOWN | |||
~ ~ ~ l ~ | |||
i '-i "l I 1 i 100 200 Egg 420 | |||
.,)NDICATED RM }}P.11 (Pgj) | |||
FIGURE 3/g 3L@-g RCS PRESS/TEMP,LIMI!TS (0 - 'l5 Mg ~ pggpg.i~~~g PALO VERDE - UNIT .3/4 4I-Z) | |||
Ik 8 | |||
REJECT Q. | |||
G CONT.I N NE TESTI N 6 | |||
@. ~ | |||
0 10 20 '0 40 50'$ V8 $8 90 I 00 FIGURE 4.7-1 SAt1PLING PLAN FOR SNUBBER FUNCTliBHRL Ilk~i PALO VERDE - UNIT $ 3/4 7-26 | |||
II ik 0 | |||
Transition Temperature Shift 'F 200 | |||
( | |||
m Kl C7 m | |||
150 100 0 | |||
hb Q | |||
I C) o~ 00 CIO 101 10 10 NEUTRON FLUENCE 0 A5338 CL 1 PLATE 0 WELD METAL FIGURE B 3/4.4-1 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E > 1 MeV) | |||
NEUTRON FLUENCE (550 F IRRADIATION) | |||
'LVINTERSBURG ROAD | |||
~ | |||
Pyi | |||
't | |||
'r i"r Qqt UNIT 1 HET UNIT 2 TOWER UNIT 3 | |||
~ 4 | |||
~. ~ | |||
'i | |||
~ ~ I~ | |||
ILP 2r. | |||
ir V | |||
~J | |||
~ E,r:. | |||
~ ', | |||
LEGEND ELLIOT ROAD CENTERLINE'OF CONTAINMENT (V/ARD ROAD) | |||
PROPERTY PURCHASED EXCLUSION BOUNDARY SITE BOUNDARY NQA TH PROPFRTY PURCHASED r//rr.. OUTSIDE EXCLUSION AREA 0 | |||
SI TE 'At<D EXCLUSIGH SOU)'CEDAR I Eg SCALE t'ai)ifgi) | |||
I"IGURE 5.1-1 5-2' PALO VERDE U"IIT | |||
, ~ | |||
0 il J | |||
0 | |||
0 0 0 W | |||
0 C | |||
~' | |||
C M | |||
lr ~ r 0 | |||
sE C C 0 v c I Vr | |||
~ | |||
V V 0 C V w C C 0 Vl q J RR~ | |||
0 0 C 0' | |||
C h C | |||
C C C C C z 3 C C I C s ~ ~ | |||
~ ~ | |||
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g I | |||
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~ I I I h | |||
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I ri I ~ ~ 1 h ~ 1 r 1 "Y/ | |||
I A. ~ | |||
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~ ~ I hC I \ | |||
ll ~ | |||
I 'h I ~ | |||
Is .1 III h ~ | |||
ii i 1 | |||
I I I ~ll I r. | |||
~ | |||
I | |||
~ | |||
.,v I I | |||
1.' | |||
~ ~ p hS l~ ~ | |||
1 s. ~ | |||
0'iQ< I | |||
~( | |||
sr I ~ I j Q rr ~ 0 s | |||
~ | |||
I: s I | |||
~ '~y.is | |||
~ I I I i | |||
~ I I~ | |||
I I h ~ I | |||
~ C ~ ~ 11 | |||
~ .I 1 I | |||
vr% | |||
~ | |||
~ | |||
' .I | |||
'C ri I ~ | |||
~ I ( | |||
thr ~ | |||
I | |||
,I \h'I | |||
~ ~ 1 Ils I ~ | |||
~ ~ | |||
I I~ 'I -C-/ i:I- 'I I'e | |||
~ | |||
~ | |||
J I I | |||
~ | |||
/l ~ | |||
I.Ql 'g,s | |||
~ C | |||
~ r I' | |||
I ~ | |||
~ '\ ~ I | |||
~ | |||
~r LOW POPULATION ZONE PALO VERDE NUCLEAR GENERATING STATION FIGURE 5 1-2 PALO VERDE - UNIT% 5-3' | |||
II ll'l 0 | |||
CEO EXECUTIVE V.P. | |||
OIR. PROJECT SERVICES V.P. NUCLEAR PRODUCTION PIR, CORPORATE PA HGR. NUCLEAR SAFETY ISEG/NSG ASST. V.P. NUCLEAR PROOUCTION HGR. PROJECT. CONTROLS ASST. HGR CORPORATE PA l ONSITE HGR. AOHIN. SERVICES PVNGS TRANSITION OIR. TECHNICAL SERVICES l PLANT MANAGER MGR. EHPLOYEE RELATIONS I | |||
HGR. OPERATIONS f | |||
/ HGR. NUCLEAR ENGINEERING I | |||
HGR. PUAI.ITY SYSTEHS/ | |||
ENGINEERING HGR. PROCUREHENT PUALITY HGR. CONTRACTS HGR. MAINTENANCE HGR. NUCLEAR CONSTRUCTION C PURCHASING HGR. PUALITY AUOITS/ | |||
MONITORING MGR. OUTAGE HGR. RECOROS MGR. PARTICIPANT SERVICES MANAGEMENT ONSITE HGR. PUALITY CONTROL HGR. PLANT SERVICES HGR. NUCLEAR FUELS HGR. EHERGENCY PLANNING ON SITE HGR. LICENSING FIGURE 6.2-1 OFFS I TE ORGANI ZATION | |||
1i il' Cl | |||
TABLE 3.'3 5 (C~~'ltfNÃgQ ENGINEERED SAFETY FEATURES RESPMBE 7KNES INITIATING SIGNAL .AND FUNCTION !Pemmax ~<<,Z Cm SZCONDS | |||
: 8. Steam Generator Level - High | |||
: a. Main Steam Isolation | |||
: 1. MSIS actuated MSIV's R.S"-/i%i..6"~ | |||
: 2. . MSIS actuated MFIV's¹ M.s //~5JP | |||
: 9. Steam Generator hP-High-Coincident 'Qith: Mani Kemrrathw Eavelt Kaw | |||
: a. Auxiliary Feedwater Isolation 35i //Ilsr from the Ruptured Steam Generrtev | |||
: 10. Control Room Essential Filtration h~a5zorrr 3JMP'~//L89F~'~ | |||
: 11. 4.16 kV Emergency Bus Undervo)Cage (Degraded Voltage) | |||
Loss of Power 90K system voltage | |||
: 12. 4.16 kV Emergency Bus Undervoltage gloss mt 9/xPjthgp)) | |||
Loss of Power TABLE NOTATIONS Diesel generator starting and, sequence loaÃzg @claps inrrcil~ Response time limit includes movement of valves .and ~imrtmC ~ff guns car Mevter discharge pressure. | |||
"~Diesel generator starting delays not inctu5&l. W7~'i'Lw guar ~va~la'b'.l~. | |||
Response time l.imit includes movement of vailzmr, ~nd adÃm5lrtma& eti pump or. | |||
blower discharge pressure. | |||
¹MFIV valves tested at simulated operating cmrmM59mm" wa.lees tt~~ at | |||
-4+VHu- | |||
~ | |||
Qcsponhp. | |||
%Rip 0& gAOlA xi~ ~ | |||
static flow conditions to 8.6/8.6 Qwb~W<M.,MOA~s ~ ~~~~M seconds. | |||
l<N gy ~+ ~flCWM~Q 2LTL X<A< )~~~~~s | |||
~ ~ | |||
~z 5Qg-Q<- So | |||
~~~gugyAC'&5 | |||
~~i+ ~+ ~ +~A'n+ ~->~ ~ -,~gg gn,-'~~~~g | |||
~, A PALO VERDE - UNIT 2 3/4 3-.29 | |||
il 0 | |||
INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 ws a minimum, the fire detection instrumentation for each FPER detection zone shown in Table 3.3-11 shall be OPERABLE. | |||
APPLICABILITY: Mhenever equipment protected by the fire detection instrument is required to be OPERABLE. | |||
ACTION: | |||
: a. With any, but not more than one-half the total in any fire zone Function X .fire detection instrument shown in Table 3.3-11 inoperable, restore the inoperable instrument(s) to OPERABLE status within 14 days or within the next 1 hour establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours or monitor the containment air temperature at least once per hour at 6 aP the locations listed in Specification 4.6. 1..5. | |||
: b. With more than one-half of the Function X fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Function Y fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour establish a fire watch patrol. | |||
to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5. | |||
8oP= | |||
C. The provisie6s of Specifications 3.0.3 and 3.0.4 are not applicable. | |||
'SURVEILLANCE RE UIREMENTS 4.3.3.7. 1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAl TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTOOMN exceeding 24 hours unless performed in the previous 6 months. | |||
4.3.3.7.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. | |||
PALO VERDE - UNIT 2 3/4 3-6O | |||
0 Cl | |||
TABLE 3. 3-13 (Continued) | |||
TABLE NOTATION | |||
"" At all times. | |||
During GASEOUS RADWASTE SYSTEM operation. | |||
0 During waste gas release. | |||
N 'n MO ES 1, 2, 3, and 4 or when irradia""d fuel is in the fuel storage pool. | |||
ACTION 35- With the number of channels O."EP/'.BLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release: | |||
a0 At least two independent samples of the tank's contents are analyzed, and | |||
: b. At least two technically qualified members of. the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway. | |||
ACTION 36- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. | |||
ACTION,37- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of (A) or (B) are performed: | |||
: a. Initiate the Preplanned Alternate Sampling Program of Specification 6.16 to monitor the appropriate parameter(s). | |||
: b. Place moveable air monitors in-line or take grab samples at 'least once per 12 hours. | |||
ACTION 38 " With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. | |||
ACTION 39- With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the GASEOUS RADWASTE SYSTEM may continue provided grab samples are taken and analyzed daily. With both channels inoperable operation may continue provided grab samples are taken and analyzed (1) every 4 hours during degassing operations, and | |||
: (2) daily during other operations. | |||
PALO YERDE - UNIT 2 3/4 3-74 | |||
0 ik 0 | |||
G S. | |||
wl Cast HOWVOVWE OATE SUBJECT SWEET No. | |||
CHECKED BY DATE JOB NO. | |||
Action 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the following action of (A) or (B) are performed: | |||
: a. Place movable air monitor in-line | |||
: b. Take grab samples at the mode specific frequencies indicate below. | |||
Monitor Mode 6 5 4 3 2 1 RU-141 N/A iV/A D D S S RU-143 M M D D S S RU-145' M M M M M Vent shall be sampled daily while moving irradiated fuel. | |||
II | |||
~O | |||
TABLE 4.6-1 TENOON 'SURVEILLANCE -,FIRST YEAR Tendon Visual Monitor Oetension Remove Test No. Inspection Forces Tendon Mire Mire V43 | |||
+ Ha No | |||
'No, No No No No X | |||
+'o ~ No pP'~ .~ ADo V62 | |||
(,A') V75~ | |||
H13-007< | |||
~ X X | |||
X 4 ga Qb A( ~ < Po )do H13-021 X + go No No No H21" 037 X ,+Ho No No ,No H21-044 X + go No No No H32"016 X + g~ No No No Q) H32-030' P'3o Notes: | |||
"X" means the tendon shown shall be inspected for the stated requirements during this surveillance. | |||
: 2. "A" means the tendon shown shall be inspected for the 'stated requirements during 'the next or second surveil.lance. | |||
: 3. "No" 'means that inspection is not required for tha't tendon. | |||
: 4. """ means control tendon. | |||
PALO VEROE - UNIT 2 3/4 6-12 | |||
, ~, | |||
0 | |||
CONTAINMENT SYSTEMS 3/4.6. 2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM h | |||
LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with earth spray system capable of taking suction from the RMT on a containment spray actuation signal and automatically transferring suction to the containment sump on a recirculation actuation signal. Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger. | |||
APPLICABILITY: MODES 1, 2, 3, and 4." | |||
ACTION Mith one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the inoperable spray system to OPERABLE status within the next 48 hours or be in COLD SHUTDOWN within the following 30 hours. | |||
SURVEILLANCE RE UIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE: | |||
a0 At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is positioned to take suction from the RMT on a containment spray actuation (CSAS) test signal. | |||
: b. By verifying that each pump develops an indicated differential pressure of greater than or equal to 27 psid at greater than or equal the minimum allowable recirculation flowrate when tested pursuant to Specification 4.0.5. | |||
C. At least once per 31 days by verifying that the system pipirg is full .of water to the 60 inch level in the containment spray header (>115 foot level).. | |||
: d. At least once per 18 months, during shutdown, by: | |||
: l. Verifying'that each automatic valve in the flow path actuates to its correct position on a containment spray actuation (CSAS) and recirculation actuation (RAS} test signal. | |||
: 2. Verifying that upon a recirculation actuation test signal, | |||
.the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established. | |||
"Only when shutdown, cooling 'is not in operation. | |||
PALO VERDE UNIT 2 3/4 6-15 | |||
'I II 0 | |||
PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-4 shalll he. QHERNBLE APPLICABILITY: Whenever equipment in the areas protected hyg tUim fives hose stations is required to be OPERABLE, except that fire hose s~ixna ligated in containment sha3-1 .have their containment isolation valves claret firn SIDES 3., | |||
2, 3, 4, and 5'CTION: | |||
ao With one or more of the fire hose stations shown %nt liakTk 3.7W inoperable, provide a gated wye on the nearest OPSTtML~Z: ihjse sation. | |||
One outlet of the wye shall. be connected to the stfarrdhndf Tfxegfh ef hose provided for the OPERABLE hose station. The sanazdl mC'ice of the wye shall be connected to a length of hose suIi5TKcti~ M ymvide coverage for the area left unprotected by the incqamaDille. Hest s+tion. | |||
The above action shall be accomplished within one Nmn'ift'%a >aoper-able fire hose is the primary means of fire supprsasnlarn;; eCtmwise provide the additional hose in 24 hours. | |||
The hose for the unprotected area shall be stored.ak N8.OMBRE hose station. Signs identifying the purpose. and 1ama@iiom eT Cibe fire hose and related valves shall be mounted above the Heaei andi at, the inoperable hose station. | |||
: b. The provisions of Specifications 3.0.3 and 3.Q.4 hei no%; agyliiic Me. | |||
SURVEILLANCE RE UIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7W) sfiaiH!ba demonstrated OPERABLE: | |||
a0 At least once per 31 days by visual inspection of ti.'ie ~axns accessible during plant operation to assure all re@mnm5 eqntlIpment is at the station. | |||
: b. At least once per 18 months by: | |||
Visual inspection of the stations 'not accessiblle dluriirng ip3ant operations to assure l,'I all required equipment is altt Chs ~Coon. | |||
: 2. Removing the hose for inspection and rerackinL, ag4 | |||
: 3. Inspecting all gaskets and replacing any degrMhdl aparkeM in the couplings. | |||
"If ~ | |||
t 1s to be performed in containment during MODE 5 %m !hre hose stations located in containment shall have their contains@ | |||
ho'+worq -< | |||
. PALO VERDE UNIT 2 3/4 7"37 | |||
I il il I I il | |||
TABLE 3.7-5 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HERE JFKMK LOCATION .HRBAWi'MISBER 150'lant North of Fuel Bldg. | |||
100'lant Mest of Rad !he+a Rldg.- | |||
150'lant Northwest of, F!!ol Bldg. | |||
"No hose house, however, the hose station is used to service ~undam~M transfer pump PALO VERDE - UNIT 2 3/4 7-41 | |||
0 il | |||
TABLE B 3/4.4-1 | |||
<774- oI REACTOR VESSEL TOUGHNESS F-71)- o L | |||
~(FORGINGS F'-77<- o > | |||
F-7~v-o4 DROP TEHPERATURE OF MINIMUM UPPER | |||
'7Q 7-ol WEIGHT CHARPY V-NOTCH~ SHELF C ENERGY P-]4 1-o E RESULTS RT NDT(b) 30 ft- lb ft-ta I 50 FOR LONGITUDINAL PIECE NO. CODE NO. MATERIAL VESSEL LOCATION ~Of } ~('F lb DIRECTION-ft lb 128-101 H-6703=1 508-CLED In'let Nozzle -20 g-gO +20 +60 N.A. | |||
128-101 128-101 H-6703-2 H-6703-3 SA SA SA 508-CLg9 508-CL2'3 Inlet Inlet Nozzle Nozzle 30 Qo M | |||
W | |||
+K.go C~ QQ | |||
-25 | |||
-27 ' | |||
+10 | |||
+18 N.A. | |||
N.A. | |||
128-101 H-6703-4 SA 508-CLED Inlet Nozzle -9o A e-qo +5 +42 N.A. | |||
131-102 M-4307-1 SA 508-CL2'I Outlet Nozzle Safe End ~-3a 4R lQ +30 +68 N.A. | |||
131-102 ~ M-4307-2 SA 508-CLZl Outlet Nozzle Safe End W-30 +8-]o +30 +68 N.A. | |||
08-4 ~~i.508-CL2 ~mB~~t~sio~~ | |||
WL%~Wet-}}ozr1e-Extenso~~ | |||
128"301 H-4 -1 SA Outlet Nozzle -10 35}((* 10}}(* N.A. | |||
12&-301 !1-4304-2 SA 508-CL2 Outlet Noizl e "10 3 5*}}'10 10}}(}}( N.A. | |||
131-101 H-6712-1 SA 508-CLl Inlet Nozzle Safe End -10 +45 N.A. | |||
131-101 H-6712-2 SA 508-CLl Inlet Nozzle Safe End ~O +10 +45 N.A. | |||
131-101 H-6712-3 SA 508-CLl Inlet Nozzle Safe End +7 +50 N.A. | |||
131-101 126-101 H-6712-4 M-6705-1 SA 50&-CLl Inlet Nozzle Safe End Z 90 80 -78 | |||
+7 +5U "28 N.A. | |||
N.A. | |||
SA 508-CL2 Vessel Flange 106-101 M-6706-1 SA 598-CL2 Closure Head Flange So "80 "54 N.A. | |||
N.A. = Not Applicable (no minimum upper shelf requirement). | |||
Lower bound curve valves. | |||
"* = Average of three test results. | |||
(a) = Determined per applicable ASME-BPV-Co'de Sect. | |||
= | |||
III, Subsection NB, Article NB-2331-(a-1,2,3). | |||
(b) 0 and 180 specimens had the same values. | |||
g le-ol F. le-O'K F-IL t -0'l | |||
: g. tl+eZ F-'4 lo-o'5 F'-'l4s.o t | |||
<- ave,- L F-1 4L-+'L | |||
~ i Ik il 0 | |||
TABLE B 3/4.4<<1 (Continued). | |||
REACTOR VESSEL TOUGHNESS (PLATES) | |||
DROP TEMPERATURE OF MINIMUM UPPER MEIGHT RT (a) CHARPY V-NOTCH" SHELF C ENERGY RESULTS NDT. 8 30 8 50 . FOR LONGITUDINAL ~ | |||
PIECE NO. CODE NO. MATERIAL VESSEL LOCATION ~F ~(rF ft - 1b ft - 1b DIRECTION-ft 1b 142-102 "4311- SA 533-GRB-CL1 Lower Shell Plate ~- (o ~ lo "6 +40 JoS 142-102 H 4311 SA 533-GRB-CL1 Lower Shell Plate <<gf <<g'g 0 "24 "8 127 142-102 H- 1 -3 SA 533-GRB<<CLl Lower Shell Plate -8f-4o A-Qo "7 . +14 %4& /gf 124-102 H-6 l-l Intermed. Shell Plate Bo +W -Ko +44 +90 ea 124-102 124-102 H-6 1-2 H- -3 SA SA SA 533-GRB-CL1 533-GRB-CL1 533-GRB"CL1 Intermed. Shell Plate Intermed. Shell Plate | |||
-Sf'-zo "30 | |||
+AS lO JQ +56 | |||
+39 | |||
+98 | |||
+89 | |||
))q 9& (g) | |||
H- 70 -4 533-GRB-CLl Upper Shell Plate "30 122-102 122-102 122"102 | |||
.H 701 5 H 6701-SA SA SA 533-GRB-CL1 Upper Shell Plate 533-GRB-CL1 Upper Shell Plate -30 fp ~ le | |||
+$ 8 cR | |||
+~ o | |||
+82 | |||
+49 | |||
+42 | |||
+120 | |||
+98 | |||
+96 N.A. | |||
N.A. | |||
N.A. | |||
102<<102PC H 6709- . SA 533-GRB"CLl Closure Head Dome W-4o +36 . +66 N.A. | |||
102<<1029 H 6709-2 SA 533-GRB"CL1 Closure Head Dome -K-su W-Qp +4 +37 N.A. | |||
. 150-102 H-6715-1 SA 533-GRB-CL1 Bottom Head Dome 25-9p $0 +2 +30 N.A. | |||
150-102 H-6715-2 SA 533-GRB-CLl Bottom Head Dome -AtLgp +26 +50 N.A. | |||
(a) = Determined per applicable ASHE-BPV-Code Sect. | |||
= | |||
III, Subsection NB, Article NB-2331-(a-1,2,3). | |||
N.A. Not Applicable (no minimum upper shelf requirement). | |||
= Lower bound curve values of transverse specimens. | |||
C-Y73-ol F'q1> oZ, f I f$-05 F'- l4b=o~( | |||
p-14$ -ob fr-z~f'ol l lp'f.oLr 5=)AD 8'-oX P lM.o3 5= 770-o I F-1aoeZ f-Tl) -O1 4= 71<-o2 | |||
0 43 TABLE 3.3=3 (Continued) | |||
ENGINEERED SAFETY FEATURES ACTUATIOH SYSTEM INSTRUMENTATION MINIMUfi TOTAL HO.'. CHANNELS CHANNELS APPLICABLE ESFA SYSTEM FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION YI. AUXILIARY FEEDWATER (SG-l)(AFAS-1) (Continued) | |||
B. ESFA System Logic | |||
: 1. Matrix Logic 6 1 2 3 17 | |||
: 2. Initiation Logic 4(c) 2(d) 1, 2, 3, 4 | |||
: 3. Manual AFAS 4(c) 2(d} 1, 2, 3, 4 15 r-.. ~ | |||
C. Automatic Actuation Logic 1 '1,2,3,4 16 C VII. AUXILIARY FEEDWATER (SG-2)(AFAS-2) | |||
A. Sensor/Trip Units | |||
: 1. Steam Generator 82 Level- Dl3 Low 1 2 3 13+ 1 4J( | |||
g s | |||
: 2. Steam Generator b, Pressure - SGl > SG2 1 2 3 13", 14" ~i a B. ESFA System Logic | |||
: 1. Matrix Logic 1,2,3 17 | |||
: 2. Initiation Logic 4(c) 2(d) 1, 2, 3, 4 12 | |||
: 3. Manual AFAS 4(c) ~ | |||
2(d) 1, 2, 3, 4 C. Automatic Actuation Logic 1 1, 2, 3, 4 16 VIII. LOSS OF POWER (LOV) | |||
A. | |||
B. | |||
: 4. 16 kV Emergency Bus Under-voltage (Loss of Voltage) | |||
: 4. 16 kY Emergency Bus Under-voltage (Degraded Voltage) 4/Bus 4/Bus 2/Bus 2/Bus P | |||
3/Bus 3/Bus 1 | |||
1'2 2 3 3 | |||
h'513K'4K 13*, 14* | |||
CONTROL ROOM ESSENTIAL 'FILTRATION 2 1 All Mode 1QA'' | |||
Q'X. | |||
CD)~1'TROD '::-9 8"f US:~P. | |||
TABLE 3. 3-3 (Continued) | |||
TABLE NOTATIONS (a) In MODES 3-6, the value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer pressure and this value is maintained at less than or equa e ual to.400 p si*; th e setpoint, shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia. | |||
(b) In MODES 3-6, the value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached. | |||
(c) Four channels provided, arranged in a selective two-out-of-four configuration (i.e., one-out-of-two taken twice). | |||
(d) The proper two-out-of-four combination. | |||
The provisions of Specification 3.0.4 are not applicable. | The provisions of Specification 3.0.4 are not applicable. | ||
After the initial criticality of Unit 2 or Unit 3~ACTION STATEMENTS | After the initial criticality of Unit 2 or Unit 3~ | ||
'.~.M'J~l J aE'Q:.Q 3'2~J~J J'ASES.REMOTE SHUTDOWN SYSTEM (Continued) | ACTION STATEMENTS ACTION 12 - .With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE | ||
The parameters selected to be monitored ensure that (lg 15m czrM5tien of the reactor is known, (2)conditions in the RCS are known, (3)dhole Meam generators are available for residual heat removal, (4)a source of watjea iir awa$1jable for makeup to the RCS, and (5)the charging system is available the maMup mat,er to the RCS.The OPERABILITY of the remote shutdown system insures%he;a imam will not preclude achieving safe shutdown.The remote shutdown sp~em%esXv~menta-tion, control and power circuits and disconnect switches neraszmg M e3iminate effects of the fire and allow operation of instrumentation, ean<~lj and power circuits required to achieve and maintain a safe shutdown mmimitixrn ave independent of areas where a fire could damage systems noma>ljljy/ | . status within 48 hours or be in at least HOT STANDBY within,the next 6 hours and in COLD SHUTDOWN within the following 30 hours. | ||
esa8 | ACTION 13 - Mith the number of charm'els OPERABLE one less than the Total Number of Channels, STARTUP andlor POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour. If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6. 5. 1. 6. h. The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN. | ||
KmMman 3 and Appendix R to 10 CFR 50.The alternate disconnect methods or power or control ciinzuIjj5s mneme that sufficient capability is available to permit shutdown and oaCnOanavme ef cold shutdown of the facility by relying on additional operator aetNenrs~M caecal control stations rather than at the RSP.3/4.3.3.6 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrune~4l~Mijam ensures that sufficient information is available on selected plant yenama~taa M monitor and assess these variables following an accident.This cap-tbiiljijdpj f>s consistent with the recommendations of Regulatory Guide 1.97,"Instrunandath'ice f'm K.ight-Mater-Cooled, Nuclear Plants to Assess Plant Conditions During andliFn'~l;lawing an Accident," December 1975 and NUREG 0578,"TMI-2 Lessons Leanm@j"jjask farce Status Report and Short-Term Recommendati'ons;" P The containment high range area monitors (RU-148&RU-lj48))anil<he main steamline radiation monitors (RU-139 A&B and RU-140 A&B)av.ijrn'T&1in 3.3-6.The high range effluent monitors and samplers (RU-142, RU-if%zmQ RD-3.46)are in Tab~le 3 g-13.The containment hydrogen monitors are in!gxecii&llea-tionC3//4.6.5.1.'he Post Accident Sampling System (RCS coolly ws im Table 3.3-6.~The Subcooled Margin Monitor (SMM), the Heat Junction>1h~ernrgcnuple (HJTC), and the Core Exit Thermocouples (CET)comprise the Inadequate Gene Cooling (ICC)ia strumentation required by Item II.F.2 NUREG-0737, the post'7~,jjIit-2.Action plan.The function of the ICC instrumentation is to enhance the abjj'llij~ | With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below. | ||
ef'the plant operator to diagnose the approach to existance of, and recook~Imam ZCC.Additionally, they aid in tracking reactor coolant inventory. | Process Measurement Circuit | ||
Mass instruments are included in the Technical Specifications at the request et lVCC Generic Letter 83-37.These are not required by the-accident analysijs rTn<M bring the plant to Cold Shutdown.PALO VERDE-UNIT 1'3/4 3-4 4 iP 0 (m | : l. Steam Generator Pressure- Steam Generator Pressure - Low Low Steam Generator Level 1-Low (ESF) | ||
=vgmfgg J 4P l1 F IGUR E 3.1-2B CORE POWER | Steam Generator Level 2-Low (ESF) | ||
z O~K~LLJ EEE 0~0 O~.G l- | : 2. Steam Generator Level Steam Generator Level - Low (RPS) | ||
PALO VEROE | (Wide Range) 'Steam Generator Level 1-Low (ESF} | ||
~7 i.XF C 0, 0}} | Steam Generator Level 2-Low (ESF) | ||
PALO VERDE - 'UNIT 1 3/4 3-23 | |||
il 0 | |||
'.~.M'J~l J aE'Q:. Q 3 '2 ~J | |||
~J INSTRUMENTATION J'ASES. | |||
REMOTE SHUTDOWN SYSTEM (Continued) | |||
The parameters selected to be monitored ensure that (lg 15m czrM5tien of the reactor is known, (2) conditions in the RCS are known, (3) dhole Meam generators are available for residual heat removal, (4) a source of watjea iir awa$ 1jable for makeup to the RCS, and (5) the charging system is available the maMup mat,er to the RCS. | |||
The OPERABILITY of the remote shutdown system insures %he; a imam will not preclude achieving safe shutdown. The remote shutdown sp~em %esXv~menta-tion, control and power circuits and disconnect switches neraszmg M e3iminate effects of the fire and allow operation of instrumentation, ean<~lj and power circuits required to achieve and maintain a safe shutdown mmimitixrn ave independent of areas where a fire could damage systems noma>ljljy/ esa8 the reactor. This capability is consistent with General Der>firqp> KmMman 3 | |||
~ shutdown and Appendix R to 10 CFR 50. | |||
The alternate disconnect methods or power or control ciinzuIjj5s mneme that sufficient capability is available to permit shutdown and oaCnOanavme ef cold shutdown of the facility by relying on additional operator aetNenrs ~M caecal control stations rather than at the RSP. | |||
3/4. 3. 3. 6 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrune~4l~Mijam ensures that sufficient information is available on selected plant yenama~taa M monitor and assess these variables following an accident. This cap-tbiiljijdpj f>s consistent with the recommendations of Regulatory Guide 1.97, "Instrunandath'ice f'm K.ight-Mater-Cooled, Nuclear Plants to Assess Plant Conditions During andliFn'~l;lawing an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Leanm@j"jjask farce Status Report and Short-Term Recommendati'ons;" | |||
P The containment high range area monitors (RU-148 & RU-lj48)) anil <he main steamline radiation monitors (RU-139 A&B and RU-140 A&B) av. ijrn 'T&1in 3.3-6. | |||
The high range effluent monitors and samplers (RU-142, RU-if% zmQ RD-3.46) are in Tab~le 3 g-13. The containment hydrogen monitors are in !gxecii&llea-tionC3//4.6.5.1.'he Post Accident Sampling System (RCS coolly ws im Table 3. 3-6.~ | |||
The Subcooled Margin Monitor (SMM), the Heat Junction >1h~ernrgcnuple (HJTC), | |||
and the Core Exit Thermocouples (CET) comprise the Inadequate Gene Cooling (ICC) ia strumentation required by Item II.F.2 NUREG-0737, the post '7~,jjIit-2 .Action plan. | |||
The function of the ICC instrumentation is to enhance the abjj'llij~ ef 'the plant operator to diagnose the approach to existance of, and recook~ Imam ZCC. | |||
Additionally, they aid in tracking reactor coolant inventory. Mass instruments are included in the Technical Specifications at the request et lVCC Generic Letter 83-37. These are not required by the-accident analysijs rTn< M bring the plant to Cold Shutdown. | |||
PALO VERDE - UNIT 1' 3/4 3-4 | |||
4 iP 0 | |||
( | |||
m | |||
't C7 .00 m | |||
0.90 I | |||
0.80 M Vl IQ f/) lR | |||
~ | |||
IA m 0.70 .H C)H M 00 0.60 | |||
~ | |||
a0 J m C | |||
~ 7t g~ fgesa C) ~ z1 0.50 Po 3 A I', A GI ION 6 | |||
I l IR y,g g | |||
I m | |||
5 jJ d)30 0 k5 I | |||
6BA Mxvl+RAt)AT = vgmfgg | |||
J 4P l1 | |||
F IGUR E 3.1-2B CORE POWER LIMITAFTER CEA DEVIATION% | |||
z O | |||
~K | |||
~ LLJ EEE 0 30 | |||
~0 20 ~ ~ ~ | |||
(60 MIN, 20%%d) | |||
O~ | |||
.G I ~ I O l- ~ I t | |||
~ O 10 D I- I~ | |||
ax UJ LZ: I g | |||
CC 0 | |||
u QO | |||
~O 0 10 20 30 40 50 60 Z TIME AFTER DEVIATION,MINUTES "WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL. | |||
POWER PER THIS LIMITCURPE, FURTHER REDUCTION IS NOT REQUIRED FIGURE 3. 1-2B CORE POMER LIMIT AFTER CEA DEVIATION~ | |||
PALO VEROE UNIT if 3/4 1-24 | |||
ll' PANGS PLANT MANAGER OUTAGEHANAGEIIENT TECHHI GAL OPERATIONS HAINTEHAHCE PLANT SERVICES HAtlAGER SUPPORT HAtlAGER HANAGER HANAGER HANAGER HAHAGER HRF SUPERIHTEtlDEtlT SUPERVISOR, ttRF HANAGER TRAINING OPS ENGIIlEERING HAINTENANCE SUPERINTEtiDENT HAtlAGER UNIT I SUPERINTENDENT OPERATIONS SECURITY ICC HAIHTENAllCE SUPERINTENDENT SUPERVISOR HAtlAGER UNIT 2 SUPERINTENOEtlT FIRE PROTECTIOH RAD. PROT. C CHEN. HCC SUPERINTENDEHT SUPERVISOR UNIT 3 SUPERIHTENDENT COHPLIANCE ELEC. HAINTENANCE SUPERVISOR SUPERINTENDENT OPERATIONS SUPPORT SUPERINTENDENT OPS COHPUTER STATION SERVICES SYSTEH SUPERINTENOEHT HECHANICAL HAINTENANCE FIGURE 6.2-2 ONSITE UNIT ORGANIZATION | |||
0 C | |||
r TNIIAO T POINT MAINSILAM SUIYUHT STHUCIUNE ~ | |||
CONTAINMENT ULUG AUXILIARYBLDG | |||
~ ~ | |||
~ VACUUMPUMP EXHAUST I | |||
TUI(BINE BUILDING FUEL BUILDING E XHAUST POINT FUELBLDG>> | |||
Ia GEN RADWASTE BUILDING 'UILDING CONTROL BUILDING 9'.2'IESEL a | |||
PL LAUNDRY'ECONTAMINATION FACILITY(UNIT I ONLYI CONT PLAN'T NORTH rI rr r S+ | |||
~ ~ | |||
I.0" PL CONT'5 112' I2a'.0 | |||
- - '246'4" I | |||
I Palu Vaadr Nuakaa Iiaucaaling Slaliw L | |||
TYI'ICAL POML'R BIDCK ExoausT poiNTs HEY pLaw IJI I | |||
Ira (elevation of exhaust point above grade) | |||
Plant Vent Building 145'uel 116'acuum 84'O-I"-86 I I | |||
Pump | |||
~7 i. | |||
XF C | |||
0, 0}} | |||
Latest revision as of 05:01, 4 February 2020
| ML17299A468 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/02/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-33162-EEVB, TAC-60706, NUDOCS 8508050402 | |
| Download: ML17299A468 (168) | |
Text
g C',
c REGULATORY li FORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR!8508050402 DOC ~ DATE: 85/08/02 NOTARI2ED: NO DOCKET FACIL:STN 50 529 Palo Verde Nuclear Stationr Unit 2g Arizona Publi 05000529 AUTH, NAME AUTHOR AFFILIATION VANBRUNT.E~ Arizona Publ ic Ser vice'o, RECIP ~ NAMEI RECIPIENT AFFILIATION KNIGHTON g*G ~ Pl ~ Licensing Branch 3
SUBJECT:
Forwards marked-up draft Tech Specs<per util.850712 commitment~Corrections<comments<graphsitablesrfigures'8 Justifications included. Meetings to resolve issues or~
Questions scheduled for. 850805 L 06 at NRG ~
AJ DISTRIBUTION CODE: B001D COPIES RECEIVED:LTR .
TITLE: Licensing Submittal: PSAR/FSAR Amdts 8 Related Correspondence NOTES:Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT , COPIES ID CODE/NAME. LTTR ENCL= ID CODE/NAME LTTR ENCL<
NRR/DL/ADL-NRR LB3 LA 1
1 0 0 NRR LB3 LICITRArE BC 01 1
1 0
1 INTERNAL ACRS 41 6 ADt1/LFMB 1 0 ELD/HDS3 1 0 IE F ILE. 1 1 IE/DEPER/EPB 36 1 1 IE/DQAVT/QAB2'1 1 1 NRR ROErM ~ L. NRR/DE/AEAB 0 NRR/DE/CEB NRR/DE/EQB il 13, 1
1 2
1 1
2 NRR/DF/EHEB NRR/DE/GB 28 1
1 2
1 2
NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 24 1 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFEB40. 1 1 NRR/DHFS/LQB 32 1 1>>
NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0.
NRR/DSI/AEB 26 1 1 NRR'/DSI/ASB 1 1 NRR/DSI/CPB 10. 1 1 NRR/DSI/CSB 09 1" 1 NRR/DSI/ICSB 16 1 1 NRR/DSI/METB 1 1 NRA/DSI/PSB 19 1 1 /RAB 22'4 12'RR/D 1 1 NRR/DSI/RSB 23 1 1 1 1 RGN5 3 3 RM/ /MIB 1 0.
J EXTERNAL: 24X DMB/DSS (AMDTS)
NRC>> PDR PNL" GRUEL'gR 02".
1 1
1 1
1 1
1 LPDR,'
IC .'5 BNL(AMDTS ONLY) 03"'S 1
1 1
1 1
1" TOTAL NUMBER OF COPIES REQUIRED>>'TTR 52 ENCL
t 1 0 0 A a
ll Pt a
Arizona Nuclear Povver ProJect P.O. SOX 52034 o PHOENIX, ARIZONA85072-2034 Mr. George W. Knighton, Chief ANPP-33162-EEVB/JRP Licensing Branch No. 3 August 2, 1985 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station Unit 2 Docket No. 50-529 Plant Technical Specifications (Draf t)
File: 85-055-026
Reference:
Dear Mr. Knighton:
Reference 1 transmitted to ANPP a "Draft" copy of PVNGS Unit 2 Technical Specifications. ANPP was to review this draft and make appropriate comments and changes. By copy of Reference 2, ANPP supplied the first set of comments along with a revised schedule as to the need date of Unit 2 Tech. Spec.
issuance. We also identified that marked up tables, graphs and figures would be supplied by August 15, 1985.
By copy of this letter, all the corrections, comments, graphs, tables and figures for PVNGS Unit 2 Tech. Specs. and their justifications are being transmitted to you. Meetings to resolve these issues, or any questions, are to be held August 5 and 6, 1985, in your offices.
The next step is the issuance and review of the PVNGS Unit 2 proof and review.
8508050402 850802 PDR ADOC'K 05000529 g A PDR
<<I II I, <<f l<<
II I,
I II 5 I.
Mr. George W. Knighton, Chief U. S. Nuclear Regulatory Commission Page Two ANPP-33162-EEVB/JRP If you have any questions, please contact me.
Very truly yours, GLA~
E. E. Van Brunt, Jr.
Executive Vice President Prospect Director EEVB/SRF/)le cc: Director, Region V, USNRC E. A. Licitra R. P. Zimmerman S. Brown
Justifications For Enclosed PVNGS Unit 2 Tech. Spec. Changes The following pages contain administrative changes such as typographical and unit specific number changes.
Index VIII Add Cathodic protection to 3/4 8.1.
pg. 3/4 3-5 Action 2 Change 6.5.1.6.h to 6.5.1.6.G. There is not an Item h.
Index XIII Add Cathodic protection pg. 3/4 1-21 Item C2a add Figure 3.1.2a.
pg. 3/4 3-12 Delete the last 2 sentences in the 8$/ Footnote. Table 3.3-2a does not exist. The table for the CPL addressable constants was deleted for all CE units.
pg. 3/4 3-13 Delete reference to Footnote 9 for Item C.2 "Channel Functional Test." The old footnote is deleted and the new footno'te doesn't apply to CPC's.
pg. 3/4 3-14 Item III.A. "Channel Functional Test" change Footnote 10 to 9. Footnote 10 does not exist.
pg. 3/4 3-15 Delete old Footnote 9 because the 2.2.2 Tech. Spec. no longer exists. Change Footnote 10 to 9.
3-49 Typo's, unit specific numbers and added verbage for PS'g 3/4 3-50 switch identification.
Pg. 3/4 3-51 Pg. 3/4 3-52 3/4 3-53 PS'S'g. 3/4 3-54 PS'S'/4 3/4 3-64 3/4 6-30 3/4 7-42
il l
l
pg. 3/4 7-41 Action b. Delete "...In recirculation Mode..." and add the word "operation" in its place. This is a typo. When action A was changed between Unit 1 Low Power License and Full Power License the change to Action b. was not made.
,pg. 3/4 8-3 Delete Item B and use insert. This brings our Spec. into compliance with the previously approved McGuire Spec.
which was an agreed position between NRR and ANPP during PVNGS Unit 1 Pull Power License changes. Footnote 0 Remove "This".
pg. 3/4 8-5 Delete Item 5 This is replaced with Item C.2 on pg. 3/4 8-3a.
Change Item d to e Typo.
8-7 Change Items g to f and f to g Typo.
3/4 8-16 Typo's, unit specific numbers and added verbage for over-PS'S'S'g.
3/4 8-23 current devices.
3/4 8-24 3/4 8-26 3/4 8-27 3/4 8-28 3/4 8-29 3/4 8-34 3/4 8-35 3/4 8-37 3/4 8-38 3/4 PS'S'S'S'S'S'S'S'S'S'S'S'S'S'S'S'/4 8-39 3/4 8-40 3/4 8-43 3/4 8-44 3/4 8-45 3/4 8-46 3/4 8-47 3/4 8-48 3/4 8-49
n a t'P n
1
~,
t
pg. 3/4 8-8a Cathodic Protection Add this Spec. to be consistent with 'Unit l.
pg. 3/4 9-1 Change 40 gpm in action statement to 26 gpm. This is to be consistent with changes made in 4.1.2.2.b.
pg. 3/4 10-1 Same as above.
pg. B3/4 3-4 3/4.6.5.1 should be changed to 3/4 6.4.1.
The following graphs are being supplied for the PVNGS Unit 2 Tech. Specs.
pg. 3/4 1-5 pg. 3/4 1-12 pg. 3/4 1-23 pg. 3/4 1-24 pg. 3/4 1-31 pg. 3/4 1-32 pg. 3/4 2-6 pg. 3/4 2-7 pg. 3/4 2-10 pg. 3/4 3-10 pg. 3/4 4-28 pg. 3/4 4-30 pg. 3/4 7-26 pg. B3/4 4-10 pg. B3/4 5-2 pg. B3/4 5-3 pg. B3/4 5-4 pg. B3/4 6-3 pg. B3/4'-4 pg. 3/4 3-29 Item 10 Add H "180+/180+*H" "H The response time for monitors XJ-SgA-RU-29 and XJ-SgB-RU-30 to trip on radiation is not included in the response time measurements for dampers M-HJA-MOl, M-HJA-M52, M-HJB-M01 and M-JHB-M55."
This clarifies that the monitors are not included in the response time measurements for dampers.
r-
"i E
I, II I
pg. 3/4 3-6 Add "5 of" to action statements A and B.
a "...per hour at 5 of the ..."
b "...per hour at 5 of the ..."
These additions are to bring Spec. 3.3.3.7 in agreement with Spec. 4.6.1.5.
pg. 3/4 3-74 Replace Action 37 with insert. This change is being made to bring the Tech. Spec., Preplanned Alternate Sampling Program and Region V desires into compliance.
pg. 3/4 6-12 Make noted changes in Table 4.6-1 to bring PVNGS Unit 2 Tech. Specs in compliance with Reg. Guide 1.35 Section C.1.3 and C.3.
pg. 3/4 6-15 Suxveillance 4.6.2.1.6. Change 273 psid to 275 psid.
T11is change is based on test data.
pg. 3/4 3-22 Item IX deleted 8 under applicable modes. This footnote is no longer applicable.
pg. 3/4 3-23 Delete footnote No longer applicable.
pg. 3/4 7-41 Change hydrant numbers as shown. These are unit specific.
pg. B3/4 4-8 Change numbers as shown to make applicable to Unit 2.
pg. 3/4 3-36 Delete CIASA K205 CIASB K205 as per recent design change. These are now spares.
)
~ A I
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.85080504a2 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 7 PLANT SYSTEMS 3/4. 7..1 TURBINE CYCLE SAFETY VALVES................................. ~ ~ ~ ~ ~ ~ ~ 3/4 7"1 AUXILIARY FEEDMATER SYSTEH..................... 3/4 7-4 CONDENSATE STORAGE TANK............-........-. 3/4 7-6 3/4 7-7 MAIN STEAM LINE ISOLATION VALVES.............. 3/4 7-9 ATMOSPHERIC DUMP VALVES............-.-.-.-...- 3/4 7-10 3l4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.. 3/4 7-11 3/4..7. 3 ESSENTIAL COOLING MATER SYSTEH................... 3/4 7"12 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM.......................... 7-13 3/4.7. 5 ULTIMATE HEAT SINK.................................. 3/4 7-,.14 3/4.7. 6 ESSENTIAL CHILLED MATER SYSTEM...................... 3/4 7-15 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM............ 3/4 7-16 3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM............ 3/4 7-19 3/4o 7o 9 SNUBBERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3l4 7-21 3/4.7.1O SEALED SOURCE CONTAMINATION.................. 3/4 7-27 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION MATER SYSTEM....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-29 SPRAY AND/OR SPRINKLER SYSTEMS...... 0 ~ ~ ~ 3/4 7-32 C02 SYSTEMS.......................... 3l4 7-35 FIRE HOSE STATIONS ~ ~ ~ ~ ~ ~ ....-3/4 7" 37 YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES. 3/4 7-40 HALON SYSTEMS.................. 3/4 7-42 3/4.7.12 FIRE-RATED ASSEMBLIES...........;................... ~ ~ ~ ~ 3/4 7-43 3/4.7.13 SHUTDOWN COOLING SYSTEM....,.............. - - - .. -... -. ~ ~ ~ ~ 3/4 7"45 3/4.7. 14 CONTROL ROOM AIR TEMPERATURE...... -... - . - - - - .. - .. - . ~ ~ ~ 0 0 3l4 7-46 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES OPERATING.. 3/4 8"1 SHUTDOWN;.. 3/4 8-8
~~D~.PACKS':VXO~ . $ 3~$
PALO VERDE - UNIT 2 VIII
4I O~
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INOEX BASES SECTION ~
PAGE 3/4.7 PLANT SYSTEMS 3/4.7. 1, TURBINE CYCLE......'.......-....... -... - .. -..... B 3/4 7-1 3/4.7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION......... B 3/4 7-3 3/4.7..3 ESSENTIAL COOLING WATER SYSTEM.......................... B 3/4 7-3 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM........,...............-..>>.. B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK...................................... B 3/4 7-4 3/4 7o6 ESSENTIAL CHILLED WATER, SYSTEM.......................... B 3/4 7-4 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM................ B 3/4'7-5 3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM................ B 3/4 7-5 3 /4.7. 9 SNUBBERSo ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ o ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION............................. B 3/4 7-7 3/4.7.11 FIRE SUPPRESSION SYSTEMS....................,............. B 3/4 7-7 3/4.7.12 FIRE"RATED ASSEMBLIES........... B 3/4 7-8 3/4.7.13 SHUTDOWN COOLING SYSTEM............. B 3/4 7"8 3/4.7.14 CONTROL ROOM AIR TEMPERATURE............................ B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2', and 3/4.8.3 .A.C. SOURCES, D.C. SOURCES, and
~ OHSITE POWER DISTRIBUTION SYSTEMS........:....... B 3/4 8-1 3/4.8.4 ELECTRICAL EgUIPMEHT PROTECTIVE DEVICES................. B 3/4 8-3 3/4. 9 REFUELIHG OPERATIONS 3/4o go 1 BORON CONCEHTRATIONo ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 9-1 3/4. 9. 2 INSTRUMENTATION.... B 3/4 9-1 3/4. 9. 3 DECAY TIME........ B 3/4 9-1 1
3/4. 9. 4 CONTAINMENT BUILDING PEHETRATIONS. B 3/4 9-1 3/4. 9. 5 COMMUNICATIONS B 3/4 9-1 PALO VERDE " UNIT 2 XIII
$$ ~
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REACTIVITY CONTROL SYSTEMS 3/4. 1. 3 MOVABLE CONTROL ASSEMBLIES CEA POSITION LIMITING.CONDITION FOR OPERATION
- 3. 1.3. 1 All full-length (shutdown and regulating) CEAs, and all part-length CEAs which are inserted in the core, shall be OPERABLE with each CEA of a given group positioned within 6.6 inches (,indicated position) of all other CEAs in its group. In addition, the position of the part length CEAs Groups shall be limited to the insertion limits shown in Figure 3. 1-2A.
APPLICABILITY: MODES 1" and 2".
ACTION:
- a. With one or more full-length CEAs inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b. With more than one full-length or part-length CEA inoperable or misaligned from any other CEA in its group by more than 19 inches (indicated position), be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C. With one or more full-length or part-length CEAs misaligned from any other CEAs in its group by more than 6.6 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with Figure 3. 1-2B and that within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the misaligned CEA(s) is either:
- 1. Restored to OPERABLE status within its above specified alignment requirements, or
- 2. Declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3. 1. 1. 1 is satisfied. After declaring the CEA(s) inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3. 1.3.6 provided:
a) Within 1'hour the remainder of the CEAs in the group with the inoperable CEA(s) shall be aligned to within 6.6 inches of the inoperable CEA(s) while maintaining the allowable CEA sequence and insertion limits shown on Figures 3. 1-3 a
- 3. 1-4; the THERMAL POWER level shall be restric ed pur-suant to Specification 3. 1.3.6 during subsequent operation.
3 "See Special Test Exceptions 3. 10.2 and 3. 10.4.
'ALO VERDE - UNIT 1 3/4 1-21
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TABLE 3.3-1 Continued)
TABLE NOTATIONS "With the protective system trip breakers in the"closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.
8The provisions of Specification 3.0.4 are no applicable.
(a) Trip may be manually bypassed above 10-4X of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10-~X of RATED THERMAL POWER.
(b) Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia.
(c) Trip may be manual.ly bypassed .below lX of RATED THERMAL POWER; bypass shall'e automatically removed when THERMAL POWER is greater than on equal to. 1X of RATED THERMAL POWER.
(d) Trip may be bypassed during testing pursuant to Special Test Exception
- 3. 10. 3.
(e) See Special Test Exception 3.10.2.
(f) There are four channels, each of. which is comprised of one of the four reactor trip breakers, arranged in a selective two-out-of-four configuration (i.e., one-out-of-two taken twice).
ACTION STATEMENTS ACTION 1 With the number'f channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the protective system trip breakers.
ACTION 2 With the number of channels OPERABLE one less than tne- Tota'l
.Number'i': .Channels STAFTUP and/"<'OWER OPERATION may. conti i-provided the inoperable channel is placed in the bypassed or tripped condition .within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the inoperable channel is bypassed, the desirabi.lity of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5:1.6.j('he channel ehail be returned to OPERABLE status no later than during the next COLD SHUTDOWN.
PALO VERDE - UNIT 2 3/4 3-5
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TABLE 3.3-2 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME II. RPS LOGIC A. Matrix Logic Not Appl icable B. Initiation Logic Hot Applicable III. RPS ACTUATION DEVICES A. Reactor Trip Breakers Not Applicable B. Manual Trip Not Applicable Neutron detectors are exempt from response time testing. The response time of the neutron flux signal portion of the channel shall be measured from the detector output or from the input of first electronic component in channel..
Response time shall be measured from the output of the sensor. Acceptable CEA sensor response shall be demonstrated by compliance wi'th Specifica-tion 3.1.3.4.
OThe pulse transmitters measuring pump speed are exempt from response time testing. The response time shall be measured from the pulse shaper input.
¹¹Response time shall be measured from the output of the resistance temperature detector (sensor). RTD response time shall be measured at least once per 18 months. The measured response time of the slowest RTD shall be less than or e 3 secon A gus ments to t e C a ressa e constants given in Table 3.3-2a s all be made to accomodate current values of the RTD time constants. If the RTD time constant for a CPC channel exceeds the value corresponding to the penalties currently in use, the affected be declared inoperable until penalties appropriate to the new time channel(s)'hall constant re installed.
¹¹¹Response time s a 1 be measured from the output of the pressure transmitter.
The transmitter response time shall be less than or equal to 0.7 second.,
PALO VERDE - UNIT 2 3/4 3-Z2
TABLE 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS
(
m CD m CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE VIREO Z
M I. TRIP GENERATION A. Process
- 1. Pressurizer Pressure - High S R M 1 2 2.
1 Pressurizer Pressure - Low S R M 1 2
- 3. Steam Generator Level - Low S R M 1$ 2
- 4. Steam Generator Level - High S R M 11 2
- 5. Steam Generator Pressure - Low S R M g 1 2 3)k
- 6. Containment Pressure - High S R M' 1 2
- 7. Reactor Coolant Flow - Low S R 1 2
- 8. Local Power Density - High S' D (2, 4), R (4, 5) M, R (6) 1$ 2
- 9. DNBR " Low 0 (2, 4), R (4, 5) M, R (6) 1 2 M (S), S (7)
B. Excore Neutron Flux
- l. Variable Overpower Trip 0 (2, 4}, M (3, 4) 1 2 C (4)
- 2. Logarithmic Power, Level - High R. (4} M and S/U (1) 1, 2, 3, 4, 5 and "
C. Core 1.
2.
Protection Calculator System CEA Calculators Core Protection Calculators D R ',R(6)
(2, 4), R (4, 5) ';M (9) R (6)
I 1,2 1, 2 )
M (B), S'(7)
1 Oi
TABLE.4.3-1 (Continued)
REACTOR PR TECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS
(
Pl Kl Cl CHANNEL MODES IN MHICH foal CHANNEL CHANNEL FUNCTIONAL . SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE UIRED D. Supplementary Protection System Pressurizer Pressure - High 1, 2 II. RPS LOGIC 1
A; Matrix Logic N.A. N.A. 1, 2, 3", 4+, 5"
- 8. Initiation Logic N.A. N.A. 3A 4* Pk III. RPS ACTUATION DEVICES I A. Reactor Trip Breakers N.A. N.A. M, R'-P9,0):; . 1, 2, 3", 4*j 5" B. Manual Trip N.A. N.A. M 1 2 3A 4A 5A
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TABLE 4.3-1 Continued)
TABLE NOTATIONS With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.
Each STARTUP or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if ro performed in the previous .7 days.
(2) Heat balance only (CHANNEL FUNCTIONAL TEST not included), above 15K of RATED THERMAL POWER; adjust the linear power level, the CPC delta T power and CPC nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than 2X. During PHYSICS .
TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.
(3) Above 15K of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
After each fuel loading and prior to exceeding 70K of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall use these elements.
(6) This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the charm'el as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions.
(7) Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is less than or equal to the actual flow rate. The flow measurement uncertainty may be included in the BERRl term in the CPC and is equal to or greater than 4X.
(s) Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differentral pressure instrumentation and the ultrasonic flow meter adjusted pump curves or calorimetric calculations.
thl CHANNEL FUNCTIONA vent>cation that~ (~(z t
CPC per-Specification 2.2.2.
. At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the .undervoltage and shunt trips.
PALO VERDE " UNIT 1 3/4 3-X5
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SMITCH DISCONNECT SMITCHES LOCATION SG 1 1-ine 2 Atmospheric Dump'dai~~ Qiovc o Alit v RSP Val ve~ SGB-HY-178A Ann SOS-H). nS R,
- 3. Auxiliary Spray Valve RSP CHB-HV-203
- 4. Letdown to Regenerative RSP Heat Exchanger I olation, CHB-UV-515
- 5. Reactor Coolant Pump RSP Controlled Bleedoff, CHB-HV-505 Auxiliary Feedwater Pump RSP B to SG 1 Control Valve, AFB-HV-30
- 7. Auxiliary Feedwater Pump RSP B to SG 2 Control Valve, AFB-HV-31
- 8. Auxiliary Feedwater Pump RSP B to SG 1 Block Valve, AFB-HV-34
- 9. Auxiliary Feedwater Pump RSP B to SG 2 Block Valve, AFB-HV-35
- 10. Pressurizer Backup Heaters Banks RSP B10, B18, A05 Control Safety Injection Tank 2A RSP Vent Control SIB-HV-613
- 12. Safety Injection Tank 2B RSP Vent Control SIB-HV-623
- 13. Safety Injection Tank 1A RSP Vent Control SIB-HV-633
- 14. Safety Injection Tank 1B RSP Vent Control SIB-HV-643
- 15. Safety Injection Tank Vent RSP Valves Power Supply SIB-HS-18A aso~c~~~
- 18. Control BLDG Battery Room 0 PHB-M3205 Essential Exhaust Fan Battery
'JB-JOIA'ontrol
- 19. BLDG Room B PHB-M3206 Essential Exhaust Fan Control PHB-3209 AND PKD-H14
'HJB-JOIB'attery
- 22. LPSI Pump SIB-P01 Breaker PBB-S04F Control 23.. Diesel Generator B Breaker PBB"S04B Control
- 24. Essential Spray Pond Pump SIB-P01 PBB-S04C Breaker Control PALO VERDE - UNIT 2 3/4 3-49
0
~ i
SMITCH DISCONNECT SMITCHES LOCATION
- 25. Essential Chiller ECB-801 PBB-S04G Breaker Con~t ol
- 26. E-PBB-.S04J~4.16KV Feeder PBB-S04J QQOV 27.
- 'c ms-E-PBB-S04HY4.16KV Feeder PBB-S04H Breaker o Load Center~> iodniB -I e'I
- 28. E-PBB-S04NK. 16KV Feeder PBB-S04N Breaker to Load Center~~3~ PETS-L.SLu
- 29. Auxiliary Feedwater Pump AFB-P01 PBB-S04S Breaker Control
- 30. Essential Cooling Water PBB-S04M Pump EMB-POl Breaker Control
- 31. E-PGB-L32B2F480V Main 5LBH t-+ Feeder Breaker to Load PGB-L32B2
- 32. E-PGB-L34B2%480V Main Center~3PdqS-L:BB Mpyt.g Feeler Breaker to Load PGB-L34B2
- 33. E-PGB-L36B2-480V Main Center~) P<iR - L 'b I PGB"L36B2
+PJ'S
- 34. q Fe&er Breaker to Load Center~~3 Charging Pump No. 2 CHB-P01 PC~%-WSLa PGB-L32Cl Supply Breaker CHB-POl
- 35. Diesel Engine Control DGB-C01 Switch M HS-KA
- 36. Diesel Engine Control DGB-C01 Switch M SS-2.B
- 37. Diesel Generator Control DGB-C01 Switch H>- Z
- 38. Diesel Generator Essential DGB-C01 Exhaust Fan HDB-JOl
- 39. Diesel Generator Fuel Oil DGB-C01 Transfer Pump DFB-POl
- 40. Battery Charger BD PHB-M3425 Contro1 Room Circuitef PKB-H16
- 41. Battery Charger B PHB-M3627 Control Room Circuits PKB-H12
- 42. 125 VDC Battery B Breaker PKB-M4201 Control Room Circuits
- 43. 125 VDC Battery D Breaker PKD-M4401 Control Room Circuits
- 45. Shutdown Coo 1ng LPSI Suction PHB-M3611 SIB-HV-656
- 47. Shutdown Cooling Warmup PHB-M3806 Bypass SIB-HV-690
(gal ili il~
DISCONNECT SWITCHES SWITCH LOCATION
- 50. LPSI-SD HX "B" Bypass S -HV-307 PHB-M3803'HB-M3611
- 51. SI Pump "B" Recirc ~
-UV"668
- 52. SI Pump "B" Suction I 'IIII5~5
~
PHB-M3805
- 57. V Outlet Isolation NHN-M7208 CHN Ol
- 59. Shutdown Cooling Temperature PHB-M3416 Control SIB-HV-658
- 60. Shutdown Cooling Heat Exchanger PHB-M3416 Bypass Valve SIB-HV-693
- 61. 4.16 KV Bus PBB-S04 PBB-S04K Feeder from XFMR NBN-X04
- 62. 4.16 KV Bus PBB-S04 PBB-504L Feeder from XFMR NBN-X03
- 63. Electrical Penetr ati on Room B PHB-M3640 ACU HAB"Z06
- 65. O.S.A. Supply Damper HJB-M02 66.
67.
68.
69.
O.S.A. Supply Damper HJB-M03 R.C.S. Sample Isolation Valve SSA-UV-203 R.C.S.'ample Isolation Valve SSB-UV-200 125 VDC Battery A Breaker
~
RSP RSP SSB SSA-404-RSP'KA-M4101
~9
-Control. Room Circuits PALO VERDE - UNIT 2 3/4 3-51
il
~
SMITCH CONTROL CIRCUITS LOCATION Auxiliary Feedwater Pump B to S/G 1 RSP Isolation Valve AFB-UV~34
- 2. Auxiliary Feedwater Pump B. to S/B 1 RSP Control Valve AFB-HQ30
- 4. Auxiliary Feedwater Pump B to S/G '2 RSP Control Valve AFB-H~31
- 5. Auxiliary Feedwater ~ump PBB-S04S AFB-Pol Charging Pump No. 2 PGB-L32C4 CHB"P01
- 7. Pressurizer Auxiliary Spray RSP Valve CHB-HV203
- 8. Pressurizer liackup Heater Bank RSP
~
Valve CHB-UV515
- 10. RCP Cont Ble~e off RSP Valve CHB-UVP05 Volume Contr~o ank Outlet NHN"M7208 Isolation Valve CHH-U~551
- 12. RMT Gravity Feed Isolation NHN-M7209 Valve CHE-HV536
~
- 13. 5/G I line 2 Atmospheric Dump Valve Controll~lt RSP x SGB-HI C-178B
- 14. S/G line 2 Atmospheric DumpQAulu. 5ci~hcilo giaZhLATI~ RSP Valve SGB-HY-178A ~>> Sha-Hq-
- 15. 1 line 2 Atmospheric DumpUAiv~ S~~~
lib'/G Valve SG -HY-178B AAD 5hb-g,q.~gag p;g~~q~~~ RSP
- 16. S G 2 line Atmospheric Dump yAi ~~ ~~~~~,.-g RSP SGB HIC-185
- 17. S/G 2 1 ine 1 Atmospheric Dump Va~vc So~~oio Aim 2'So. RSP Val vd SGB-HY-185A Woo SCABS
- 19. D>ese1 enerator B Output PBB-S04B Breaker
'20. Diesel Generator Building DGB-B01 Essential Exhaust Fan HDB-JOl
- 21. Diesel Generator B Fuel Oil e
~ pgg-5o'lH ~
22.
Transfer 4.16 KV to Pumo DFB-P01 480V kE-~
DGB" B01 PBB-S04H
~'P~ 50++~23 K~ ~~~ bR ~K.~~
--PSS 5044
~ 4.16KV o 4.16KV to 480V 80V p,g.
PBB-S04J PBB-S04N
- 25.
- PGB-L32B2
- 26. f51- PGB-L3482 Supply Breaker ~ ~~~ gGL>~<<>< > <><
PALO VERDE - UNIT 2 3/4 3"52 s
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SWITCH CON TROL CIRCUITS LOCATION
- 27. 48&V-tMHLeb- 1I 'll PGB-L36B2-Supply Breaker te mAy curn.~ W8-~>i
- 28. Battery Charger PKB-H12 PHB"M3627 Supply Breaker
- 29. .Battery Charger PKD-H14 PHB"M3209 Supply Breaker
- 30. Backup Battery Charger PKB-H16 Supply Breaker PHB-M3425
- 31. Es sential Spray Pond Pump P ~SB -Pol PBB-S04C
- 32. Ess ential Cooling Water Pump EWB-POl PBB-S04M
- 33. Essential Chilled Water PBB-S04G Chi 1 1 er ECB-EOl
- 34. Battery Room D Essential PHB-M3206 Exhaust Fan HJB-JOlA
- 35. Battery Room B Essential PHB-M3207 Exhaust Fan HJB-J01B
- 37. Electrical Penetration Room B PHB-M3631 ACU Fan HAB-Z06
- 43. LPSI Pump B PBB-S04F SIB-Pol
- 44. Containment Spray Pump B PHB-M3804 Discharger to SD HX "B" Valve SIB-HV~689 45 LPSI Containment Spray from PHB-M3810 SD HX "B" X-tie Valve SIB-HV~95
- 46. Shutdown Cooling LPSI Suction PHB-M3605 Valve SIB- 656
- 47. Shut own oo~ing warmup Bypass PHB-M3806 .
Valve SIB-89696 Q%-4 la
- 48. LPSI Containment Spray to "B" PHB-M3414 SO HX X-tie Valve SIB-.HV694 PALO VERDE - UNIT 2 3/4 3-53
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SWITCH CONTROL CIRCUITS LOCATION
- 51. LPSI Pump 8 Recirc. PHB-M3609 v~1 ve SIB-UV6ee- 4 4S
'52. LPSI Pump 8 Suction PHB-M3805 From RWT SIB-HY~92-
- 53. RC Loop to Shutdown PHB-M3604 Cooling Valve SIB-U~652
- 54. RC Loop to Shutdown PKD-844 Coolin Valve S -UV~654
- 55. LPSI Hea er 8 to RC PHB-M3606 Loop 2A Valve SIB-UV~615 LPSI Header 8 to RC PHB-M3621 Loop 28 Valve SIB-UV625
- 57. SBC "B" Temperature control Val.ve PHB-M3412 SIB-HV-658
- 58. Control Room Ventilation Isolation ~ ~ ~ ~ 4 QQp HJB-M01/HJB-M55 'ampers
- 59. O.S.A. Supply Damper HJB-M02 ~ ~ ~ ~ ~ ~- g.bP
- 60. O.S.A. Supply Damper HJB-M03 - - - ~ .
~ ~
P Diesel Generator "8" Emergency Start eve 61.
- 62. Normal Offsite Power Supply Breaker PBB-S04K
- 63. Alternate Offsite Power Supply Breaker PBB"S04L
- 64. Battery "8" Breaker PKB-M4201
- 65. Battery "D" Breaker PKD-M4401
- 66. RCS Sample Isolation Valve SSA-UV-203 ~
SSA-~
'~G-
- 67. RCS Sample Isolation Valve SSB-UV-200 ~ ~ ~ ~ ~ ~
woq
- 69. Shutdown Cooling Heat Exchanger Bypass PHB-M3413 Valve SIB-UV-693
- 70. Battery "A" Breaker PKA-M4101 PALO VERDE - UNIT 2 3/4 3-54
0 TABLE 3. 3-11'(Continued)
FIRE DETECTION INSTRUMENTS FIRE ELEVATION INSTRUMENT LOCATION TOTAL NUMBER OF INSTRUMENTS" ZONE HEAT FLAME SMOKE (ay) (x/y) 'x/y) 34A P 'r(lp '.iTi. - Train A 2/0 7O'0' 348 ECW Pump Rm. - Train 8 2/0 35A Shutdown Cooling Ht.
FAC HM~
a~~".i 4/0 Train A 358 7o'O'0 Shutdown Cooling Ht.
~<4A~i+
ae-&gr. 4/0 Train 8
'36 I Reactor Makeup and Boric 1/0 Adddk pk p
37C 70'& Piping Penetration Rm.- 5/0 88'0'&
Train A 37D Piping Penetration Rm. 4/0 88'0'o'S'8'CW Train 8 378 Corridors - East 11/0 37A Corridors West 11/0 39A Pipeways - Train A s/o 398 Pipeways Train B 8/0-42A 100'lect. ~
Tr. A Penetration (Chan. C)
Rm. 0/1 0/25 428 Penetration Rm. 0/1 0/24 1OO'00'lect. Tr. 8 (Chan. 8) 42C Corridors - East 8 Southeast 0/2 3/35 42D
- West 0/1 2/29 46A 100'OO'00'00'orridor Charging Pump and Valve 0/3 Gallery Rm. - Train A 46B Charging Pump and Valve 0/3 Gallery Rm. - Train 8 Charging Pump and Valve 0/3 Gallery Rm. - Train E PALO VERDE - UNIT 2 3/4 3-64
0 TABLE 3.6-1 (Continued}
CONTAINMENT ISOLATION VAl VES MAXIMUM ACTUATION VALVE PENETRATION TIME NUMBER NUMBER FUNCTION (SECONDS)
F. NORMALLY OPEN " ESF ACTUATED CLOSED SG-UV 170 ¹ 1 Main steam isolation N.A.*
SG-UV 171¹ ,2 Main steam isolation N.A.~
SGE-UY 169¹ 1 Ec 2 Main steam isolation bypass N.A.
SG-UV 180¹ 3 Main steam isolation N.A."
SG-UV 181¹ 4 Main steam isolation N.A."
SGE-UV 183¹ 3 8( 4 Main steam isolation bypass N.A.
SGA-UY 1133¹ 1-4 Steam trap/bypass N.A.
SGA-UV 1134¹ 1"4 Steam trap/bypass N.A.
SGB-UV 1135A¹ 1-4 Steam trap/bypass N.A.
SGB-UV 1135B¹ 1-4 Steam trap/bypass N.A.
SGB-UV 1136A¹ 1"4 Steam trap/bypass N.A.
SGB-UY 1136B¹ 1-4 Steam trap/bypass N.A.
SGA-UV 174¹ 8 Steam generator feedwater N. A.
SGB-UV 132¹ 8 Steam generator feedwater N.A.
SGB-UV 137¹ 10 Steam generator feedwater N.A.
SGA-UY 177¹ 10 Steam generator feedwater N.A.
C SGB-UY 130¹ 11 .Downcomer FIV N.A.
~ ~
SGA-UV 172¹ 11 .Downcomer FIV N. A.
SGB-UV 135¹ 12 Downcomer FIY N. A.
¹Not Type C tested '3 "Valves also covered by Specification 3/4:7. .4 PALO VERDE - UNIT 2 3/4 6-30
il 0
PLANT SYSTEMS HALON SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.6 The following Halon systems shall be OPERABLE.
- a. Train A Remote Shutdown Panel Room, Zone 10A - Control Building 100 ft. Elevation
- b. - -.Train B Remote Shutdown Panel Room, Zone 10B - Control Building 100 ft. Elevation APPLICABILITY: Mhenever equipment protected by the Halon system is required to be OPERABLE.
ACTION:
Nth one or more of the above required Halon systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fire~
suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.?.118aEach. of the above required Halon systems shall be demonstrated OPERABLE:
ae At least once per 31 days by verifying that each valve (manual, power-operated, or automatic} in the flow path is in its correct position.
- b. At least once per 6 months by verifying Halon storage tank weight to be at least 95K of full charge. weight and, pressure to be at least 90K of full charge pressure.
\
C. At least once per 18 months by:
Verifying the system actuates manually and automatically, upon ,
receipt of a simulated test signal, and S
- 2. Performance of g flow test through headers and nozzles to assule no blockage."
PALO VERDE - UNIT 2 3/4 7-42
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ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)
- 4. Verifying the diesel starts from ambient condition and acceler-ates to at least 600 rpm in less than or equal to 10 seconds."
The generator voltage and frequency shall be 4160 + 420 volts and 60 1.2 Hz within.lO 'seconds after the start signal. The diesel generator shall be started for this test by using one of the following signals:
a) Manual.
--b) Simulated loss-of-offsite power by itself.
c} Simulated loss-of-offsite power in conjunction with an ESF actuation test signal.
d) An ESF actuation test signal by itself.
- 5. Verifying the generator is synchronized, loaded to greater than or equal to 5500 kW in less than or equal to 5 minutes, and operates with a load greater than or equal to 5500 kW for at least an additional 60 minutes, and
- 6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
- b. A t once per 31 days and after each o 1 Sa.q where the peri reater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by <<Sa.r or and removing accumulated water rom e a nks.
c; By sampling new fuel oil in accordance with ASTM D4057-81 prior to addition to the storage tanks and:
- 1. By verifying in accordance with the tests specified in ASTM D975-81 prior to addition to the storage tanks that the sample has:
a) An API Gravity of within 0.3 degrees at 60 F or a specific gravity of within 0.0016 at 60/60'F, when compared to th.=..
supplier's certificate or an absolute specific gravity at 60/60 F of greater than or equal to 0.83 but less tha;.
oJ equal to 0.89 or an API gravity at 60'F of greater than or equal to 27 degrees but less than or equal to 39 degrees, b) A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by comparison with the supplier's certification, The diesel generator start (10 seconds) from ambient conditions shall, be per-formed at least once per 184 days in hese surveillance tests. All other.en-gine starts for the purpose of surveillance testing may be preceded by an engine prelube period and/or other warmup procedures recommended by the manu-facturer so that mechanical stress and wear on the diesel engine is minimized.
PALO VERDE - UNIT 2 3/4 8-3
Ii 0
kAS a.r paxnKb
0 0
ELECTRICAL POMER SYSTEM SURVEILLANCE RE UIREMENTS (Continued
~ <~i "-t.~Y ther properties specified i of ASTM-D975-19?7 ~akim~
and Reg ory Guide 1. evision 1, October 1979, Posi-analysis 's tion 2.a., whe e comp ut may be performed a in accordance with ASTM-D975-1977; within 14 days after obtaining 'e addition of new fuel o l.
A swgg Sos..rr., ;/A-t least once Per 18 .months during shutdown by:
- 1. ".
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its.manufacturer's recommendations for this class of standby service.
- 2. Verifying the generator capability to reject a single largest load of greater than or equal to 839 kM (Train B AFW pump) or 696 kM (Train A HPSI pump) while maintaining voltage at 4160 + 420 volts and frequency at 60 + 1.2 Hz.
- 3. Verifying the generator capability to reject a load of 5500 kM without tripping. The generator voltage shall not exceed 6240 volts during and following the load rejection.
- 4. Simulating a loss-of-offsite power by itself; and:
a) Verifying deenergization of the emergency busses and load shedding from the emergency busses.
b) Verifying the diesel starts on the auto-start signal, energizes the emergency busses with. permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After'ner'gization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 + 420 volts and 60 + 1.2/-,0.3 Hz during this test.
- 5. Verifying that on an ESF actuation test signal (without loss-of-offsite power) the diesel generator starts on the auto-start signal arid operates on standby for greater than or equal to 5 minutes. The steady-state .generator voltage and frequency shall be 4160 + 420 volts and 60 + 1.2 Hz within 10 seconds after the auto-start signal; the generator voltage and frequency shall be maintained within these limits during this test.
6.. Simulating a loss-of-offsite power in conjunction with an ESF actuation test signal, and PALO VERDE UNIT 2 3/4 8-5
0 ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)
- 11. Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross connection lines.
- 12. Verifying that the automatic load sequence timer is OPERABLE with the interval between each load bloc'k within + 1 second of its design interval.
- 13. .Verifying that the following diesel generator lockout features
. prevent diesel generator starting only when required:
a) (turning gear engaged) b) (emergency stop)
At least once per 10 years or after any modifications which covld affect diesel generator interdependence by starting the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to at least 600 rpm (steady-state generator voltage and frequency of 4160 + 420 volts and 60 + 1.2 Hz) in less than or equal to 10 seconds.
.'At least once per 10 years by:
- 1. Draining each fuel oil. storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or the equivalent, and
- 2. Performing a pressure test of those portions of the diesel fuel oil system designed .to Section III, subsection ND of the ASME Code at a test pressure equal to llOX of the system design pi essure.
4.8. 1. 1.3 ~Re orts All diesel generator failvres, valid or nonvalid, shall be reported to the Commission within 30 days in a Special Report pursuant to Specification 6.9.2. Reports of diesel generator failures shall include the information recommended in Regulatory Position C. 3. b. of Regulatory Guide 1. 108, Revision 1, August 1977. If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1. 108, Revision r 1, August 1977.
PALO VERDE - UNIT 2 3/4 8-7
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0
ELECTRICAL POWER SYSTEMS A.C. SOURCES LIMITING CONDITIONS FOR OPERATION 3.8. 1.3 The Cathodic Protection System associated with the Diesel Generator Fuel Oil Storage Tanks shall be OPERABLE.
APPLICABILITY: At al 1 times.
ACTION:
- a. With Cathodic Protection System inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of malfunction and the plans for restoring the system to OPERABLE status.
- b. The provisions of Specification 3; 0. 3 and 3. 0. 4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.8. 1.3 Ver ify that the Cathodic Protection System is OPERABLE at the follow-ing time intervals:
Verify at least once per 92 days that the Cathodic Protection rectifiers are OPERABLE and have been inspected in accordance with Regulatory Guide 1. 137.
- 2. Verify at least once per 18 months that the Cathodic Protection is OPERABLE and providing adequate protection against corrosion in accordance with Regulatory Guide 1. 137.
PALO VERDE - UNIT Z- 3/4 8-Ba
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il il
ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS OPERATING LIMITING CONDITION FOR OPERATION 3.8.3.1 The following electrical busses shall be energized in the specified manner with tie breaker open between redundant busses within the unit.
- a. Train "A" A.C. emergency busses consisting of:
- 1. 4160-volt ESF Bus ¹E-PBA-S03
- 2. 480-volt ESF Load Center ¹E-PGA-L31
- a. MCC E-PHA-M31
- 3. 480-volt ESF Load Center ¹EPGA-L33
- a. MCC E-PHA-M33
- b. MCC E-PHA-M37
- 4. 480-volt ESF Load Center ¹E-PGA-L35
- a. MCC E-PHA-M35
- b. Train "B" A.C. emergency busses consisting of:
- 1. 4160-volt ESF Bus ¹E-PBB-S04
- 2. 480-volt ESF Load Center ¹E-PGB-L32
- a. MCC E-PHB-M32
- b. MCC E-PHB-M38
- 3. 480-volt ESF Load Center ¹E-PGB-L34
- a. MCC E-PHB-M36
- c. 120-volt Channel A Vital A.C. Bus ¹E-PNA-025 energized from its
,associated inverter connected to D.C. Channel A."
- d. 120-volt Channel B Vital A.C. Bus ¹E-PNB-026 energized from its associated inverter connected to D. C. Channel B. *
- e. 120-volt Channel C Vital A.C. Bus ¹E-PNC-02? energized from its associated inverter connected to D.C. Channel C.*
120"volt Channel 0 Vital A.C.. Bus ¹E-PND-028 energized from its associated inverter connected;to D.C. Channel D."
- g. 125-volt D.C. Channel A energized from Battery Bank E-PKA-Fll.
- h. 125-volt D.C. Channel B energized from Battery Bank E-PKB-F12.
125-volt D.C. Channel C energized from Battery Bank E-PKC-F13.
125-volt D.C. Channel D energized from Battery Bank E-PKD-Fl4.
"Two inverters may be disconnected from thei~ Q.C. bus for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, as necessary, for the purpose. of performing an equalizing charge on their associ-ated battery bank provided (1) their vital busses are energized, and (2) the vital busses associated with the other battery bank are energized from their associated- inverters and connected to their associated D.C. bus.
PALO VERDE - UNIT 2 3/4 8"16
i~
4k 0
TABLE 3. 8-2 (Continued}
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-NHN-M1533 E-NHN-M1502B REACTOR CAVITY FAN D DISCH DAMPER M-HCN-M02D E-NHN-M1534 E-NHN-M1535 CTMT BLDG MONO HOIST 1 TON M-ZCN-~ CgOQ E-NHN"M1517 E" NHN-M1535 REACTOR COOLANT OIL LIFT PUMP M-RCN-P02A E-NHN-M1902 E-NHN"M1917A REACTOR CAVITY NORM CLG FAN M-HCN-A03A E-NHN-M1904 E-NHN-M1917B REACTOR CAVITY NORM CLG FAN M"HCN-A03C E-NHN-M1907 E-NHN-M1917 CEDM NORM ACU-A HEXCH OUTLET VLV J"NCN-HV-485 E-NHN-M1911 E-NHN-M1917 CTMT NORM ACU"C CHILLED WTR INLET VLV J-WCN-HV-59 E-NHN-M1912 E-NHN-M1917 CTMT NORM ACU-A CHILLED WTR INLET VLV J-WCN-HV-57 E-NHN-M2008 E-NHN-M2010 CEDM NORM ACU-B HEXCH OUTLET VLV J"NCN-HV-486 E-NHN-M2003 E-NHN"M2010 CTMT NORM ACU-B CHILL WATER INLET VLV J-WCN-HV-58 E-NHN-M2004 E-NHN"M2010 CTMT NORM ACU-D CHILL WATER INLET VLV J-WCN"HV-60 E-NHN-M2006 E-NHN-M2010A REACTOR CAVITY NORM CLG FAN M-HCN"A03B E-NHN-M2007 E- NHN-M2016 REACTOR CAVITY NORM CLG FAN M-HCN-A030 E"NHN"M2803 E"NHN-M2827A CEDM ACU C INTAKE DAMPER M-HCN-M03C E-NHN-M2804 E"NHN-M2827A CEDM ACU D INTAKE DAMPER M-HCN-M030 PALO VERDE " UNIT 2 3/4 8"23
~,
0
TABLE 3.8-2 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIYE DEYICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-NHN-H2805 E-NHN-M2827A SGl COLD LEG BLOWDOWN ISO VLV J"SGE-HY-41 E-NHN-H2806 E-NHN-M2827B SG HOT LEG BLOWDOWN ISOLATION VALVE J"SGE-HY-43 E-NHN-H2827 E-NHN-H2827A REACTOR COOL PUMP OIL LIFT PUMP lB H"RCN-P02BP E-NHN-H2828 E"NHN-H2827A REACTOR COOLANT PUMP OIL LIFT PUMP 2B M-RCN-P02DP E-NHN-H2809 E"NHN-M2827C CONTAINMENT E(UIP HATCH J-ZCN-E02 E-NHN-M2811 E-NHN-M2832A 30A RECEPTACLES FOR CTMT BLDG JIB CRANE g-%CA-C)0"fA)Q E-NHN-M2818 E-NHN-M2832A 30A RECEPTACLES FOR SEAL CRANE ASSY MOT E-NHN-M2817 E" NHN-H2832B CTMT BLDG MONORAIL HOIST 1 TON M-ZCN-G03 E" NHN-M2819 E-NHN-M2832B 30A RECEPTACLES JIB CRANE ~~
FOR CTMT BLDG Q- EC.Q- (0+ A]Q E"NHN-M2820 E-NHN-M28320 CTMT BLDG ELEY ¹2 CONTROLLER J" ZCN-E01 E" NHN"H2821 E-NHN-M2828C MULTIPLE STUD TENSIONER M"ZCN-M15 E"NHN-M2822 E-NHN-M2828B WELDING RECPTS E-NHN"I09 '
B, C, D
~ ll E" NHN-M2801A E"NHN-M2827B FUEL TRANSFER SYS CONTROL CONSOLE E-PK-002 E"NHN"M2833 E"NHN-M2827B REFUELING MACHINE E-PC J02 E"NHN-M2833A E-NHN-M2827B CEA CHANGE PLATFORM E-PC-JQl PALO VERDE - UNIT 2 3/4 8-24
~ i 0
TABLE 3.8-2'(Continued)"
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E"PGB"L34D2 E-NGN-B34D2 CEDM NORMAL ACU FAN (FUSE) M-HCN-A01D E-PGB-L34D3 E-NGN-B34D3 CEDM NORMAL ACU FAN (FUSE) M-HCN"A02D E-PGB-L36D3 E-NGN-B3603 CTMT NOR ACU FAN M-HCN-A01B (FUSE)
E-PHA-M3318 E-PHA-M3334 SAFETY INJECT TANK 4 ISOL VLV J-SIA"UV"644 E- PHA-M3316 E-PHA-M3316A SAFETY INJECT TANK 3 ISOL VLV J"SIA-UV"634 E-PHB-M3404 E"PHB-M3405B NCMS RET INT CTMT ISOL VLV J-NCB-UV-403
.RAA-L 8: PKA-'bzA3o CTMT PRG PMR ACCESS MODE ISO LF YLY J-CPA-UY-48',
E-PHA-M3517 E"PHA"M3521 CTMT PRG RFL MODE ISO VLV J-CPA-UY-2B E"PHA-M3503 E-PHA-M350 IA SHUT ON CLG ISOL LOOP 1 VLY J" SIA-UY-651 E"PHA-M3508 E" PHA-M3511A CTMT/RAD SUMP CTMT INT ISO VLV J-RDA"UV-23 E-PHA-M3512 E" PHA"M3513A CTMT SUMP ISOL TRAIN A VLV
- J-SIA-UV-673 E-PHB-M3622 E"PHB"M3629 CTMT PRG REFULING MODE ISO VLV J-CPB"UY-3A E-PHB-M3604 i'. c E-PHB-M3604A SHUT DN CLG ISOL LOOP 2 VLV J-SIB-UV-652 E" PHB" M3619 E-PHB-M3641A SAFETY INJECTION TANK ISOL VLY J-SIB"UY-614
%All. 6- PKS- 02ZIQ CTMT PRG PMR ACCESS MODE ISO YLY J-CPB-UY-5A PALO VERDE " UNIT 2 3/4 8"26
0 Ib
/
TABLE 3.8-2 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVIC'E BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-PHB-M3613 E" PHB" M3613A CTMT SUMP ISOL TRAIN B VLV J-S IB-UV"675 E-PHB-M3618 ... E-PHB-M3641 SAFETY INJECTION TANK 2 ISO
'VLV J-SIB-UV-624 E"PHA-M3704 E-PHA-M3703A MASTE GAS HEADER CONTAINMENT ISOLATION VALVE BRA'~
Q-@RA,- Ave E-PHA-M3715 E-PHA-M3719 Hp CONT TRAIN A UPSTM SUP ISO VLV J-HPA" UV"1 E"PHB-M3816 E-PHB-M3836 Hp CTMT TRAIN B UPSTM SUP ISO YLY'"HPB-UY"2 E- P HB-M3811 E" PHB-M3813A NORM CHIL WTR RETURN CTMT ISO
- Vl V J"MCB"UV-61 E-PKD-B44 E-PKD-M4411 SHUTDOW CLG ISOL VLV J-SID-UV-654 E- P KC"B43 E- PKC" M4311 SHUTDOW COOLING ISOL VLV J-SIC-UV"653 E-NNN-D1113 E-NNN-D11 MOVABLE INCORE DRIVE SYS ¹I 800VA, M"RIN-M03A VIA E-R IN-J01A E-NNN-D1213 E" NNN-012 MOYABLE INCORE DRIYE SYS ¹II 800VA, M-RIN-M03B VIA E-RIN- J01A E-NNN-D1526 f-NNN-D15 RCP INSTM LOCAL PNL J-RCN-E02 E-NNN-D1525 f-NNN"D15 RCP.INSTM LOCAL PNL
.J-RCN- E01 E-NNN- 01626 E" NNN-016 RCP INSTM LOCAL PNL J-RCN-E04 E" NNN-D1625 E-NNN-D16 RCP INSTM LOCAL PNL J"RCN-E03
,E"QAN"D05B E"QAN-B02 LIGHTING PANEL E-QAN-005B CTMT BLDG EL 100'ALO VERDE " UNIT 2 3/4 8-27
il~
il 0
TABLE 3.8-2 '(Continued}
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPT ION E-QAN-D05C =
LIGHTING PANEL E"QAN-005C 100'"QAN-B03 CTMT BLDG EL E-QAN"D05D - E-QAN-B04 LIGHTING PANEL E-QAN-D05D CTMT BLDG EL 140'IGHTING E-QAN-D05F E-QAN-B05 PANEL E"QAN-D05F CTMT BLDG EL 140'IGHTING E"QAN-D05E E-QAN-B06 PANEL E"QAN-D05E CTMT BLDG EL 140'IGHTING E-QBN-BOl E-QBN-D91 PANEL E"QBN-D73A CTMT BLDG EL 100'"
QBN-B02 E-QBN-091 LIGHTING PANEL E-QBN" D?3B CTMT BLDG EL 140'O E-NHN-D1514 E-NHN-M1526 OPERATION CAMERA JB¹ 2 2
E-RCN-D010$ E" NGN- L11C2 PZR BU HTR M"RCE"B07, B13, A01 E-NHN-D2614 E-NHN-M2618 TO OPERATION CAMERA JB¹ 1 E-RCN-D01% E-NGN- L11C2 PZR BU HTR M"RCE-B03, A09, A15 t
E-RCN"D030g E-NGN- L11C3 PZR BU HTR M"RCE-B04, All, A16 E-RCN-0030k E-NGN- L11C3 PZR BU HTR M-RCE-A02, AO?, A13 l
E-RCN-D0202 E-NGN- L12C2 PZR BU HTR M-RCE-B06, B12, A18 E" RCN" D020Y E" NGN"'L12C2 PZR BU HTR M"RCE-B16, A04, A08
". E-RCN-0040 E-NGN-L12C3 PZR BU HTR M-RCE-B15, A03, Alo E-RCN-D040 E" NGN- L12C3 PZR BU HTR M"RCE-A17, A06, A12 PALO VERDE UNIT 2 3/4 8-28
0 0
TABLE 3.8-2 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY,DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER 'DESCRIPTION E-NAN-SOlM E-NAN-S01A RCP M-RCE-P01A (C.E. NO. 1A)
E-NAN"S03B E-NAN-S01L E-NAN-S01A RCP M"RCE-Pole (C.E. NO. 2A)
E-NAN"S03B E"NAN-502L E-NAN-S02A 'RCP M"RCE-P01B (C.E. NO. 1B)
E-NAN-S04B X E-NAN-SO M f"NAN-S02A RCP M"RCE"P01D (C.E. NO. 2B)
E-NAN-S04B E"NGN-L03C2 FUSE IN BKR. CTMT NOR DUCT HTR M-HCN"Eolc E-NGN"L03C3 FUSE. IN BKR. CTMT NOR DUCT HTR M-HCN-E01Q E-NGN-L03D2 FUSE IN BKR. CTMT POLAR CRANE M-ZCN-GOl E-NGN-L06C2 E-NGN-BOGC2 CTMT PRE-ACCESS NORM AFU FAN (FUSE) M-HCN-F01A E-NGN-L09C4 E-NGN-B09C4 CTMT PRE-ACCESS NORM AFU FAN (FUSE) M-HCN-F01B E-NGN- L10C2 FUSE IN BKR. 'CTMT NORM DUCT HTR M- HCN" E01A E-NGN- LlOC3 FUSE IN BKR. CTMT NORM DUCT HTR M-HCN" E01B f~ ggg e p( jQQQ I
PROPORTIONAL HTR BANK M-RCE"B2, QFu.X B8 B14
- RH- ~stoa F-Q&,Q - QLZ.C.Q PROPORTIONAL HTR BANK M-RCE-B5, 7-U 'bZ. Bll, B17 CEA 06 CB101 F101, F102, F103 CEA 06 CEA 08 CB102 F104, F105,, F106 CEA 08 CEA 10 CB103 F107, F108, F109 CEA 10 PALO VERDE - 'UNIT 2 3/4 8-29
II 0
~O
TABLE 3. 8-2 '(Continued)"
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION CEA 51 CB103 F107, F108, F109 . CEA 51 CEA 53 CB104 F110', Fill, F112 CEA 53 CEA 30 CB101 F101, F102, F103 CEA 30 CEA 31 CB102 F104, F105, F106 - CEA 31 CEA 32 CB103 F107, F108, F109 CEA 32 CEA 33 CB104 F110, Fill, F112 CEA 33 CEA 01 CB101 F101, F102, F103 CEA 01 E-PHA-D33-03 E-PHA-M3332 INDICATING LIGHTS FOR VLV J"SIA"UV"634
~
E-PHA-D33-04 E-PHA-M3332 INDICATING LIGHTS FOR VLV J"SIA-UV"644 E- P HB-D36-01 E"PHA-M3638 INDICATING LIGHTS FOR VLV '-SIB"UV"614 E"PHB-D36-02 E-PHA"M3638 INDICATING LIGHTS FOR VLV J-SIB-UV-624 E"NHN"D28-04 E-NHN-M2830 CONTAINMENT PREACCESS NORMAL AFU MOTOR SPACE HEATER FOR M"MCN-F01AH E"NHN-D28-14 E-NHN-M2830 'LOW SWITCH J"HCN"FSL-29 FOR DUCT HEATERS M"HCN-E01A AND B A<A E"NHN"028"16 E-NHN-M2830 CONTAINMENT AH5'UCT HEATERS M-HCN-EOlA AND B TEMPERATURE CONTROL J-HCN-TC-29 E"NHN"D28"18 E-NHN-M2830 'LOW SWITCH J"HCN-FSL"31 FOR DUCT HEATERS M-HCN-Eolc AND 0 E" NHN-D13-04 E" NHN"M1329 CONTAINMENT ACU DUCT HEATERS M-HCN-Eolc AND 0 TEMPERATURE CONTROLLER J-HCN"TC-31 PALO VERDE - UNIT 2 3/4 8"34
il~
li
. TABLE 3'.8-2 (ContinLre@
CONTAINMENT PENETRATION KNPiJK'ffiaff OVERCURRENT PROTECTIVE I%K~
PRIMARY DEVICE BACKUP DEVICE SERVICIE NUMBER NUMBER DESCRIPTWN E-NHN-D13-22 E-NHN-.M1329 STEAM GEiEMh(IGRf N&il'ctQUP RBtttfP MOTE SPMK fHiWiEiR MI.88~KUIH E-NHN-D15-01 "-. E-NHN-M1526 REACTOR UQKNlfl BUMP.'%ÃSE MRCE HEAKiR FiBKMH&fMI RGKw7JXLB E-NHN-D15-02 E-NHN-M1526 'REACTOR HSluTii'UMP'%ME 5FAK HEATERf CM6%5RRf'rRQK-;BflTiiiBQ E-NHN-D15-06 E-NHN-M1526 FAN ~f CONTAINMBffll'ZKGGKGK'HGHIIINL N88 SBNCIE &K%% QKA~~'R M-Hcifti~'P'@XSAM ~ %
'E-NHN-D10-01 E-NHN-M1027 REACTOR. CBV~Q'UMIP M03i'QRf, SNKZ
'HEATEU Gi&Rr@HRHf Ql.RfLi-:HQZLNB E-NHN-D10-02 E-NHN"M1027 REACTOR Cmui. N1li W)PIP tNJTDff %MR HEATER ~FQkQQR hl 963-:H%EDI E-NHN-D10-20 E-NHN-M1027 STEAM GENBQgfM< %fEIl LiAV(8P 5M'RMRH<'~ifhKll!B3 HUNR'OTOR E-NHN-D19-05 E"NHN-M1914 CEDM NORMAl. AQS IiAh'I tel"82i KM%
HEATER BI.IHltff.Nial E-NHN-D19-06 E-NHN-M1914 CEDM NORMAL NUN KMI;h$7i,RRf MME HEATER Qi. Pc(Uf HNK'rH E-NHN-D19-07 E-NHN-M1914 CONTAINMENT 0ERNLi. NiBj iRNI.MSIKfR SPACE llFNtlW tiff Ni&N2LNI E-NHN-D19"08 E-NHN-M1914 CONTAIN'IENT NSfHM'Q. 4EQJ llama iViSliXE
.) a SPACE. HHKER ti~ftfff-.4%IlZHl E-NHN-D19-10 E-NHN-M1914 REACTOR .CAVITY MIRML XZEQ3M,FkM:
~ 4 MOTOR SPRITZ HE2%KRf
'e, M"HCN-AQ3NM C
E-NHN-019"12 E" NHN-M1914 REACTOR CAVGV( HfafftlM CMIQNEI SPME I!EAWERf IF'OTOR M-HCN"AEKHI PALO VEROE - UNIT 2 3/4 8-35
Il TABLE 3.8-2 (Continued),
CONTAINMENT PENETRATION CONDUC'HE OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-ZAB-C06 E-PKB-D2221 SAFETY INJ TAN( lbhK'!RGB'EI SURD.'7< VAlVE (FUSE) J-SIB-~622 Hv .
E-ZAB-C06 E-PKB-D2221 SAFETY INJ TANK VLF Wl!%E (FusE) J-SIB-HV-613 E"ZAB"C06 E-PKB-D2221 SAFETY INJ TANK'/GNW VN!VK (FUSE) J"SIB"HV"623 E-ZAB"C06 E-PKB-D2221 SAFETY INJ TANK VHH'i3'NlVE:
(FusE) J"SIB"HV-633 E-ZAB-C06 f-PKB-D2221 SAFETY INJ TANK VGi9% VMS (FusE) J-SIB-HV-643 E-ZJA"C01 E-PKA-D2101 SAFETY INJ TANK KGlRQZHHI NRPLV( ViÃVE (FUSE) J-SIA"HV-639 E-Z JA" C01 E-PKA-D2101 SAFETY INJ TANK MKGlRQEM SMBPlLV( VIVE (FUSE) J-SIA-HV-649 E-ZJA-C03 E- PKA-D2111 RCP CONTROLLED BllHDSBF 70 Rlott VihD'tE (FUSE) J-CHA-HV-507 E-ZJA"C03 E-PKA-D2111 LETDOWN LINE TG RGBKS'BE% EXCH!"L'.iM'SO VALVE (FusE) J" CHA"HV"516 E-ZJA-C03 E- PKA"D2111 RCP CONTROL'LED B'QiEBGEiF %l VKH %fA'LVE (FUSE) J"CHA"UV"506 E-Z JB-C01 E" PKB"D2201 SAFETY INJ TANK F311lL NM EMEN MLLE (FusE) J-SIB"UV-641 E-ZJB-C01 E" PKB" 02201 SI TANK CHECK VXflMK L!EK~ 299 VALVE (FusE) J-SIB-UV-648 E-ZJB-C01 ~ E-PKB-D2201 HOT LEG INJECT XHEKK VALI! IliMfNBE ISO VLV (FUSE) J-SIB" UV-322 E-ZJB-C01 E- P KB-02201 SAFETY INJ TANK NIHMGBH SERPENS VALVE (FUSE) J-SIB-Pf-632 Hv'ALO VERDE " UNIT 2 3/4 8-37
41 TABLE 3.8-2 (Continued)
CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEYICES PRIMARY'EVICE BACKUP DEVICE SERVICE NUMBER 'NUMBER DESCRIPTION E-Z JB-COl E"PKB-D2201 'AFETY INJ TANK NITROGEN SUPPLY VALVE (FUSE) J-SIP-'8-"42 lj '-ZJB-C03 E" PKB-D2211 H4'ETDOWN LINE TO REGEN HEAT EXCH VALYE (FUSE) J" CHB"UV-515 E-ZJB-C03 E- PKB-02211 SAFETY INJ TANK FILL AND DRAIN VALVE (FUSE) J"SIB-UY-631 E-ZAA-C03 , E" PKA-D2109 REACTOR DRAIN TANK OUTLET ISOLATION VALVE (FusE) J-CH UV"560 E-ZAA-C03 E-PKA-02109 SI TANK RWT HDR CTMT ISOLATION VALYE (FUSE) J"SIA"UV-682 gV E-ZAA-C03 E-PKA-D2109 REGENERATIYE HEAT EXCH TO AUX SPRAY VALVE
~@USE) J-CHA-HV-M 2oS E-ZAA-C01 , E-PKA-D2110 SAMPLE CONTAINMENT ISOLATION VALVE (FusE) J"SSA-UV-203 E"ZAA"C01 E- PKA-02110 SAMPLE CONTAINMENT ISOLATION VALVE (FUSE) J-SSA-UY-204 E -ZAA-C01 E-PKA-02110 SAMPLE CONTAINMENT ISOLATION YALVE (FUSE) J-SSA"UV"205
~~+ E-ZAA-C04 E" PKA"D2102 PRESSURIZER VENT VALVE
~(FUSE) J" RCA-HY"103 Pn E"ZAA-C05 E-PKA-02114 STEAM GEN BLO'WDOWN CTMT ISOLATION VALVE (FusE) J"SGA-UV"500P
~~
~f'-ZAA"C05 E-PKA"D2114 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGA-UV"204 E-ZAA"C05 E" PKA-D2114 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGA-UV-211 E-ZAA-C05 E-PKA-02114 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGA-UV-220 E-ZAA-C06 E- PKA-02121 SAFETY INJ TANK NITROGEN SUPPLY VALVE
'FUSE)
J-SIA-HY-619 PALO VERDE UNIT 2 3/4 8"38
Il il
!I
w~~r g m ~r, zp- e-~a.
E- z,AA-cd ~-PKA.1oz>o> gE.ACToA CooL,Axrt 9 E,~T g~us< a- RcR-Hg-l~(
Ipse,vw ~o pg z/+ s->a 6- 'RAP '-co% K-P~ ~><>G ~~ TR> QhAE.W'T PLDRQG pe~ ER
( Fu.SGQ p ~e.ss M oDE, iso>.Av <~
vA~vc-. z-c.PR -Q V- 9A
0
!I 0
TABLE 3.8-2 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-ZAA-C06 E" PKA-D2121 SAFETY INJ TANK NITROGEN SUPPLY VALVE (FUSE) J" SIA-HV-629 E-ZAA-C06 E-PKA-02121 SAFETY INJ TANK VENT VAL'VE (FUSE) J-SIA-HV-605 E"ZAA-C06 E-. PKA-D2121 SAFETY INJ TANK 'VENT VALVE (FUSE) J"SIA-HV-606 E-ZAA-C06 E" P KA-02121 SAFETY INJ TANK VENT VALVE (FUSE). J" S IA-HV-607 E-ZAA"C06 E-PKA-D2121 SAFETY INJ TANK VENT VALVE (FUSE) J"SIA-HV-608 E"ZAA"C06 E" P KA-D2121 RC 'SYSTEM VENT TO CTMT VALVE (FUSE) J-RCA-HV"106 E-ZAB-C03 E"PKB"D2209 REGEN HEAT EXCH TO AUX SPRAY VALVE (FUSE) J-CHB-HV-203 E"ZAB-C03 E-PKB"02209 REACTOR COOLANT VENT VAL'VE (FusE) J- RCB" HV-102 E-ZAB-C03 f-PKB-02209 SAFETY INJ: TANK FILL AND DRAIN VAlVE (FUSE) J-S I B-UV-611 E-ZAB-C03 E"PKB"D2209 SI TANK CHECK VALVE LEAKAGE LINE ISO VALVE (FusE) J-S I 8-UV-618 E-ZAB"C01 E- P KB-D2210 CTMT ATM RADIATION MONITORING ISO VALVE (FusE) J-HCB-UV-44 E"ZAB-C01 E-PKB-D2210 CTMT ATM RADIATION MONITORING ISO VALVE (FusE) J-HCB-UV-47 E-ZAB-C04 E-PKB"D2202 REACTOR COOLANT VENT VALVE (FUSE) J- RCB-HV-108 E"ZAB-C04 E-PKB-D2202 SAFETY INJ TANK FILL AND DRAIN VALVE (FUSE) J-SIB-UV-621 E-ZAB-C04 E-PKB-D2202 SI TANK CHECK VALVE LEAKAGE LINE ISO VALVE (FUSE) J-SIB-UV-628 p '4AQ C<h R- pKS-ORE>>. Qbk)TA114%4l4T Qci4ha f4 94hCC 4
+04 ~~>ivy, VAav~ g CPS PALO VERDE - UNIT 2 3/4'-39
0 I
0
TABLE 3.8-2 '('Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE BACKUP DEVICE SERVICE NUMBER NUMBER DESCRIPTION E-ZAB-C05 E-PKB-D2214 REACTOR COOLANT VENT VALVE (FUSE) J" RCB-HV"109 E-ZAB-C05 .. E-PKB"D2214 STEAM GEN BLOWDOWN CTMT ISOLATION VALVE (FUSE) J-SGB-UV-500R E-ZAB-C05 E-PKB" 02214 BLOWOOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J"SGB-UV"222 E-ZAB-C05 E-PKB" D2214 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J"SGB-UV-224 E-ZAB-C05 E- PKB-02214 BLOWDOWN SAMPLE CTMT ISOLATION VALVE (FUSE) J-SGB-UV-226 E-ZAB-C06 E-PKB-D2221 REACTOR COOLANT VENT VALVE (FUSE) J-RCB" HV"105 E-ZAB-C06 E-PKB-D2221 SAFETY INJ TANK NITROGEN SUPPI Y VALVE (FUSE) J-SIB-UV-612 E-ZJB-C03 E-PKB-02211 SI TANK CHECK VLV LEAKAGE LINE ISO VALVE J-SIB"UV-638 (FUSE)'"ZJB"C03 E" PKB" D2211 HOT LEG INJECT CHECK VLV .LEAKAGE ISO VLV (FUSE) J-SIB-UV-332 E-ZAN-COl E-NKN-D4226 SEAL INJECT VALVES TO RCP (FUSE) J-CHE" F V-241 E-ZAN-COl E-NKN-D4224 SEAL INJECT VALVES TO RCP (FUSE) J-CHE-FV-242 E-ZAN"C01 E"NKN-D4222 SEAL INJECT VALVES TO RCP (FUSE) J-CHE-FV-244 E-ZAN-COl E"NKN-D4224 POST ACDT SMPLG SYS ISO VALVE (FUSE) J-CHN-HV-923 E-ZAN-C01 E"NKN-D4224 REACTOR VESSEL SEAL DRAIN TO RDT VALVE (FUSE) J-RCE-HV-403 E" E-NKN-04224 SI DRAIN TO REACTOR DRAIN TANK VALVE ZAN-C01'FUSE)
J-SI E-HV-661 PALO VERDE - UNIT 2 3/4 8-40
II TABLE 3.8-3 MOTOR"OPERATED VALVES THERMAL OVERLSQS PROTECTION AND/OR BYPASS DEVICES BYPASS Ui:VICE sfslim(,$ 3 YALYE NUMBER Accident Conditions MFKGt28 J-SIA-UV-647 HPSI A Flow Control to Sx&@p 3hgert~en Reactor Coolant Yalve StQIHG&nl Dg. 5+5.
'-SIA-UY-637 HPSI A Flow Control to Rc&'bp K~WiJc)n Reactor Coolant Valve %u5dbwm EH@ 5ys.
J-SIA-HV-604 HPSI Pump A Long Term 5afiaCp Rgactann Cooling Valve RukMdh'nl K3g 5+s.
J-SIB-HV-609 HPSI Pump B Long Term SRCL~/ ZAQBUflion Cooling Valve %u55lnvm 6",ilg. Sys.
J-SIA-HV-657 Shutdown Clg. Temp. SMMivg EiqjjaMiea Control Train A Valve WuWtuvm C:ilg. Sys.
J-SI 8-HV-658 Shutdown Cl g. Temp. Ra@My Kvg~mt$ eni Control Train B Valve Nu68b%01 K tlat, S+s J-SIA-HV-685 LPSI - Ctmt Spray Pump SRCh> VnjjeW$exa Cross Connect A Valve Sdu5dbmn> Cifg., $>ys J" SIB"HV-694 LPSI- Ctmt Spray Pump 9MhNp IInjj~>en Cross Connect B Valve %L'tiltbvNl C,ltd., Syz J-SIA-HV-686 Ctmt Spray A Cross 9897aM+ ~~g~g<QQ Connect Valve %Mnltavm Z1ig Sys.
J" SIB-HV-696 Ctmt Spray B Cross SM~ Kzgertaon Connect Valve %uMwm (C~Ig. +ys.
J"SIA"HV-688 .Shutdown Clg. Heat Kagact~un Exchange A Bypass Valve XtaC~Cm<a <i;lghays.
J-SIB" HV"693 Shutdown Clg. Heat ~Wg Ztqjacttien Exchange B Bypass Yalve &uCcthurn King hays.
J-SIA-UV-617 HPSI A Flow Control To Ka~y Zagecta on React Coolant 2A Yalve 9Bv@a5nvm Cltg Sys.
PALO VERDE - UNIT 2 3/4 8-43
0 is
TABLE 3.S-3 $Ga~ixue~
MOTOR-OPERATED VALVES TFKRAM'. SSRRBD@9 PROTECTION AND/OE( EVPkSS ZEGEi BYPASS DEVICE s)7GwBK53 YALVE NUMBER Accident Condiikweae, AKFECTi,ED J-SI A"UV-627 HPSI A Flow Cori&all Te 5zi5edp Eqgecti on React Coolant '2B Vivre 'ShI.@thorn Clg.,Sys.
J-SIA-UV-645 LPSI F,low Contrail Te React Coolant O'R ~3Italiva
~i'~ Zmgacti S5uiMavm on Clg. Sys.
J-SIA-UV-635 LPSI Flow Conteeti ifh 'SiaeTa4y ejecta on React Cool ant 'l% '>Jallvm SNv@eimvm C3~g. Sys.
J-SIA-UV-644 Safety Injecthm 1~k 3$ SaiTxtipj ejection Isolation, Valve SMuNehwn Zlg.'ys.
J-SIA-UV-634 Safety Injectiera Thnk 3k SzNWy i~sgecti on Isolation Valve SMu5zhen. Llg. Sys.
J" S I B-UV.-616 HPSI B Flow CoxOmli Te "'AM@ Zrgecti on React Cool ant 2k '4~allcm Slud'ibsen> ZOg, Sys.
J"SIB-UV"626 HPSI B Flow CorCm~ll ite GRAM+ ZKQecti on React, Coolant 29 0'alum $ )Mc5uve Clig. Sys..
J;SIB-UV"'36 HPSI, B F3ow Cmtrell Ye SMxlgi Zejecti on React Coolant 3k '3htzl(ve'. SWtMuve 'C39.. Sys.
J"SIB"UV"646 HPSI B Flow Cmfuuli <te 9hcTe~~ Znjecti on React Coolant 3$ %hfl'm SlbM~a iCOg. Sys.
J-SIA"UV"655 Shutdown .Clg. M~ Sa>SM~y Zxgecti.on Isolation Loop 2 @alive~ Shura ~Clg. Sys.
J-SIB-UV"656 Shutdown Clg. ZXW Mf~p Zegection Isolation Loop 2 'EMwa Shu~wil Clg. Sys.
J-SIA-UV"664 Ctmt Spray Pump 4 Refueling Mater Tank itIo ~ Rejection SbuMnwn Cl g. Sys.
~0 Isolation Vlv.
' 1 n
PALO VERDE - UNIT 2
4I 0
TABLE 3.8-3 (Continued)
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSTEM(S)
VALVE NUMBER Accident Conditions) AFFECTED J-SIB-UY"665 Ctmt Spray Pump B Injection
'afety To Refueling Water Tank Shutdown Clg. Sys.
Isolation Vlv.
J-SIB-UY-615 LPSI Flow Control To Safety Injection React Coolant 2A Valve Shutdown Clg. Sys.
J"SIB"UV"625 LPSI B Flow Control To Safety Injection React Coolant 2B Valve Shutdown Clg. Sys.
J-SIA-UV-666 HPSI .Pump A to Refueling Safety Injection Mater Tank Isolation Shutdown Clg. Sys.
J-SIB-UV-667 HPSI Pump B to Refueling Safety Injection Mater Tank IsoIation Shutdown Clg. Sys.
J" SIA-UV-669 LPSI Pump A To Refueling Safety Injection Mater Tank Isolation Shutdown Clg. Sys.
J-SIB-UY-668 LPSI Pump B, to Refueling Safety Injection Mater Tank Isolation Shutdown Clg. Sys.
J-SIA-UY-672 Ctmt Spray Control Train A Safety Injection Yalve Shutdown Clg. Sys.
J-SIB-UY"671 Ctmt Spray Control Train B Safety Injection Yalve Shutdown Clg. Sys.
J-SIA-UY-674 Ctmt Sump Isolation Safety Injection
'.; Train A Valve Shutdown Clg. Sys.
bl J-SIB"UY-676 .'Ctmt Sump Isolation Safety Ingectson Train B Yalve Shutdown Cl g. Sys.
J"SIA"UY"651 Sh'utdown Cl g. Isol ati on Safety Injection Loop 1 Yalve Shutdown Clg. Sys.
J-SIB"UY"652 Shutdown Clg. Isolation Safety Injection Loop 2 Yalve Shutdown Clg. Sys.
PALO VERDE - UNIT 2 3/4 8-45
0 0
TABLE 3. 8-3,(Conti nued)
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSTEM(S)
VALVE NUMBER Accident Conditions AFFECTED J-SIA-UV-673 Ctmt Sump Isolation Safety Injection Train A Valve Shutdown Clg. Sys.
J-SIB" UV-675 Ctmt Sump Isolation Safety Injection Train B Valve Shutdown Clg. Sys.
J-SIB-UV-614 Safety Injection Tank 2A Safety Injection Isolation Valve Shutdown Clg. Sys.
J"SIB-UV-624 Safety Injection Tank 2B Safety Injection Isolation Valve Shutdown Clg. Sys.
J-S IA-HV"684 Shutdown Clg. Heat Safety Injection Exchange Isolation Train A Shutdown Clg. Sys.
J-SIB-HV-689 Shutdown Clg. Heat -Safety Injection Exchange Isolation Train 'B Shutdown Clg.. Sys.
J-SIA-HV-683 LPSI Pump A Isolation Safety Injection-Val ve Shutdown Clg. Sys.
J"SIB-HV"692 LPSI Pump B Iso'lation Safety Injection Valve Shutdown Clg. Sys.
J" SIA-HV-691 Shutdown Clg. Loop 2 Safety Injection Warm-Up Bypass Valve .Shutdown Clg. Sys.
J"SIB-HV"'690 Shutdown Clg. Loop 1 Safety Injection Warm-Up Bypass Valve Shutdown Clg. Sys.
J"SIA-HV"698 HPSI Pump A Discharge Safety Injection Valve Shutdown Clg. Sys.
J" SIB-HV"699 HPSI Pump B Discharge Safety Ingectson Valve Shutdown Clg. Sys.
J-SIA-HV"306 LPSI Pump A Header Safety Injection Discharge Valve Shutdown Clg. Sys.
PALO VERDE " UNIT 2 3/4 8"46
0 il
TABLE 3.8-3 (Continued)
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSTEM(S)
VALVE NUYiBER Accident Conditions) AFFECTED J-SIB-HV-307 LPSI Pump B Header Safety Injection Discharge Valve Shutdown Clg. Sys.
J-SIA-HV-687 Ctmt Spray Isolation Train A Safety Injection Valve Shutdown Clg. Sys.
J-SIB-HV-695 Ctmt Spray Isolation Train B Safety Injection Valve Shutdown Clg. Sys.
J-SIA-HV-678 Shutdown Clg. Heat Exchange Safety Injection Isolation Train A Shutdown Clg.'Sys.
J-SIB-HV-679 Shutdown Clg. Heat Exchange Safety Injection Isolation Train B Shutdown Clg. Sys.
J-SIC-UV-653 Shutdown Clg. Isolation Valve Safety Injection Shutdown Clg. Sys.
J-SID" UV-654 Shutdown Clg. Isolation Valve Safety Inject'ion Clg. Sys. 'hutdown J-EMA-UV-65 ECM Loop A To/Fi om NCM Cross Essential Cooling Tie Valve Mater System J- EMA-UV-145 ECM Loop A To/From NCM Cross Essential Cooling Tie Valve Mater System J- CTA-HV-1 Condensate Tank to Aux. Condensate Transfer Feedwater Pump Valve 8 Storage Sys.
J-CTA-HV-4 Condensate Tank to Aux. Condensate Transfer Feedwater Pump Valve 6 Storage Sys.
J-SGA-UV-134 SG-1 Aux. Feedwater Pump A Main Steam System Steam Supply J-SGA-UV"138 SG-2 Aux. Feedwater Pump A Main Steam System Steam Supply PALO VERDE - UNIT 2 3/4 8"47
II 0
TABLE 3.8-3 (Continued)
MOTOR"OPERATEQ VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSYEH(S)
VALVE NUMBER Accident Conditions AFFECTED J"NCB-UV-401 NCMS Ctmt Isolation Valve Nuclear Cooling Mater System J-NCA-UV-402 NCMS Ctmt Isolation Valve Nuclear Cooling Mater System J-NCB-UV-403 NCMS,Ctmt Isolation Yalve Nuclear Cooling Mater System i J-AFB-HV-30 Aux. Feedwater Regulating Auxiliary Feed-Valve water System '
J"AFB-HV-31 Aux. Feedwater Regulating Auxi1 iary Feed-Valve water System J-AFB-UY-34 Aux. Feedwater Regulating "Auxiliary Feed-Yalve water System J-AFB-UV-35 Aux. Feedwater Regulating Auxiliary Feed-Valve water System J"AFA-HY"32 Aux. Feedwater Regulating Auxiliary Feed-Val ve water System J-AFA-UV-37 Aux. Feedwater Isolation Auxiliary Feed-Val ve water System J"AFC-UV-36 Aux. Feedwater Isolation Auxiliary Feed; Yal ve water System J-AFC-HV"33 Aux. Feedwater Regulating Auxiliary Feed-Valve water System J-CPA-UV-2A Ctmt Purge Refueling Mode Containment Purge Isolation Valve System J-CPB-UV-3B Ctmt Purge Refueling Mode Containment Purge Isolation Valve System J-CPA"UV-2B Ctmt Purge Refueling Node Containment Purge Isolation Valve System PALO YERDE - UNIT 2 3/4 8-48
4$ ~
il 0
TABLE 3.8-3 $C~zatm8)
MOTOR-OPERATED VALVE ~iOKL SWiBHIIDMl PROTECTION AND/OR 3FPMS EEKKKS BYPASS DEVI'CE Sifts"iKMQS]}
VALVE NUMBER Acci dent Cendif%cea NFRHKTiiiB J"CPB"UV"3A Ctmt .Purge RefceTIfng ItIhM (Uanthmznnexft, Purge Isolation Valve SpMKHA J-MCA-UV-62 Normal Chill M~Nm Rhtfzen. Gati ITIT!+6 '~Rater Ctmt Isolation Spr@znn J"MCB"UV-63 Normal Chill 'M~>>, %pg>TQ~ CthÃnlt+5 ')Mes Ctmt Isolatien Spf$ 5'ellA
'J-MCB-UV-61 Normal Chal Wa5ar FNlmw GNii'iITIa4 %L~~r Ctmt Isolation Sy~
J-ROA-UV-23 Ctmt Radwas& Rmgxs K>CmnaBI Rhdlii~$vre Maste Isolation 9%89llll 5~10 J-HPA-UV-3 H2 Ctmt Train A RnvaWmsrm Smdztiimmm<~'ydrogen Supply Isolation CaMareil Sygs J"HPA"UV-5 H2 Ctmt Train A R'~me Gbn5zriizmmdt Pr4rogen Isolation Valve FezrWe)TI Syr, J"HPB"UV-4 H2 Ctmt Traaa 3 Hhe~eeam> GhnNzNrnmanII: Rgdrogen
,Supply Isolation Gmvbr+TI S~.,
J-HPB-UV-6 H2 Ctmt Train B Rhyme GhllCK181~, 39@drogen Isolation Valve E'eaCnuN 5gps J-HPB-UV-2 H2 Ctmt Train B U~tmem Emdmmment Bydrogen Supply Isolation Eam&eil Sgs.
J-HPA-UV-1 H2 Ctmt Train A SIM~naam EB'JCMXIDBllj, hydrogen Supply Isolation EmkamTI Sys.
J"GRA-UV-1 Radioactive Draira Zk: Gas (kheamm Radwaste Surge Hdr Internal ZunM5mmC ~Q'tRfm Isolation PALO VERDE - UNIT 2 3/4 8-49
0 Ib 0
3/4. 9 REFUELING OPERATIONS 3/4. 9. 1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 'Mi h.+he reactor vessel head closure boits less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is. met:
- a. Either a K ff of eff 0.95 or less, or
- b. A boron concentration of greater than or equal to 2150 ppm.
APPLICABILITY: MODE 6+.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity chagges and initiate and continue boration at greater than or equal to Z4o~gpm of a solution containing > 4000 ppm boron or its equivalent until K ~ is reduced to less than or equal to 0.95 or the boron concentration is r5ftored to'greater than or equal to 2150 ppm, whichever is the more restrictive.
SURVEILLANCE RE UIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined, prior to:
a~ Removing or unbolting the reactor vessel head, and
- b. Withdrawal of any full-length CEA in excess of. 3 feet from its,fu!:y inserted position within the reactor pressure vessel.
4.9. 1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be'determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure. bolts less than fully tensione or with the head removed..
PALO VERDE - UNIT 2 3/4 9-1
ji il 0
3/4.10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for mea urement of CEA worth and shutdown ma g n !3 Qvided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s), or'he reactor is subcritical by at least the reactivity equivalent of the highest CEA worth.
APPLICABILITY: MODES 2, 3" and 4"¹.
ACTION:
- a. With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-
,,...ately initiate and continue boration at greater than or equal to
- ~;S&~gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by.
Specification 3.1.1.1 is restored.
- b. With all full-length CEAs fully inserted and the reactor subcritical by less than he above reactivity equivalent, immediately initiate and continue boration at greater than or equal t&f& gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.l.l.l is restored.
SURVEILLANCE RE UIREMENTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdr awn shall be determined at least once per 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> s.
4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50K withdrawn. position within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the. SHUTDOWN MARGIN to less than the limits of Specification 3.1.l.l.
4.10.1.3 When in MODE 3 or MODE 4, the reactor shall be determined to be subcritical by at least the reactivity equivalent of the highest estimated CEA worth or the reactivity equivalent of the highest estimated CEA worth is. avail-.
able for trip insertion from OPERABLE CEAs at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> by con-sideration of at least the following factors:
- a. Reactor Coolant System boron concentration,
- b. CEA position,
- c. Reactor Coolant System average temperature,
- d. Fuel burnup based on gross thermal energy generation,
- e. Xenon concentration, and
- f. Samarium concentration.
Operation in MODE 3 and MODE 4 shall be limited to 6 consecutive hours.
Limited to low power PHYSICS TESTING at 'the 320'F plateau.
PALO VERDE - UNIT 2 3/4 10-1'
, ~
Ib 0
FIGURE 3.1 1
~
ALLOWABLEMTC MODES 1 AND 2 m PALO VERDE UNIT/CYCLE 1 C) m
+1.0 I
I Is I I
I ~ I
~ ~ << ~ ~'
Q 40.5 l': ):I
~ ~, I
~
40.22 x
~
jI II I Cl 1 hp/
'F , 0.0 hp /OF )
~ <<
I 4 0.22 (595 ~ ~
K ~
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4.0 coo' AVERAGE MODERATOR TEMPERATURE, F
II i/
0
136'.6" (40K) 135'-6" (30K) 135'-10"'(33 5K) ~
(
"134'-6" (20K)
..:133'-3" (7.25K).-
133'-6" (10K)
COLD S/D VOLUME 0
0 200 400 600 AVERAGE REACTOR COOLANT SYSTEM TEMP F 80)io 600 ,000 GAL. (565 F) 600 575K 75/o 573 744 G 4L (1200 F) 55nK MINIMIJniI USEFUL COLD S/D VOL. PLUS VOLUME (1) 70/o MARGIN IEQUI RED IN THE RWT RWT 5nnK LEVEL'NSTRUMENT READING (1) 65%
475K ESF VOL. PLUS MARGIN (3) 01'2) OK 200 400 609 AVERAGE RCS TEMPERATURE, F (1) THE TANK LEVEL AND VOLUMC SHQSVN ARE THE USEFUL LEVEL AND VOLUME ABOVE THAT IN THE TANK "YHICH IS REQUIRED FOR VORTEX CQNSIDERATIONS (2) DURING MODE 5 AND 6 ONE OF THESE BORATED SOURCES SHALL CONTAIN A MINIMUMOF 33,NO GALLONS (3) THIS VOLUME'IS NOT REQUIRED DURING MQPE 6 F IGUR E 3.1.2 MINIMUMBQRATED lVATER VOLUMES PALO VERGE - UNIT Q 3/4 1" 12
O~
O~
!5
FIGUR E 3.1-2A PART LENGTH CEA INSERTION LIMITvs THERMAL POWER 1.00 112.5" 0.90 0.80 ACCEPTABLE 0.70 OPERATION UNACCEPTABLE OP E RATION 0.60 0 0.50 50% POWER LINE INSERTION LIMIT 0.40 Z
0.30 u
0.20 0.10 22.5" 0.00 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 PART LENGTH CEA POSITION, INCHES WITHDRAWN
~ i ll~
C7 1.00 m
M A~
0.90 0.80 M VI I tn W~
0.70 -MQg 0 al)
C/l R 0.60 C m O X7 ~M 41 C) C) 0.50 Ag MO f en% A TRANSIENT NSE ION LIi<IT 4P lA Vl I M 0.40 W f gJ f90 I
Z Cll ~4 lA CA g 0) m 0. 30 J +~ fR.
( ln M
I 4J
$ MW Ill Q.ZO 0:10 QidO
'5U i50 30 f~O :!0 0 )50 !~C ~0 60 gg 0
/BE QXV+~UPf. = Qgggg
~
il 0
FIGURE 3.2-1 DNBR MARGIN OPERATING LIMITBASEDOIQlmi.SR (COLSS IN. SERVICE) 100 K
REGION OF 0 ACCEPTABLE
" 'I- OPERATION
~
80 U
Z }
~
0 I- LQ m C CL 0 g.
CC 0 I-
<.o R EGIN!(DH:
Lfl 40 UNA"II:ZPHAGC~E LU 0 OP ERNKHISNJ O
Ch
'0 Z 0 oZ0 C5 0
0 20 40 60 8m PERCENT OF, RATED THERMALMilSER
~ F,IGURE 3. 2-1 PNBR, MARGIN OPERATING 'LIMIT BASEP:ON UMSK (COL'SS IN SERVICE)
.PALO'ERGE - 'UNIT& 3/4 2-6
ik~
il
FIGURE 3.2-2 DNBR MARGIN OPERATING LIMITBASED ON CORE PROTECTION CALCULATOR (COLSS OUT OF SERVICE) 0.60
~ ~ ~ ~ ~
I ~
t ~ I i ~ ~ ~ v ~ ~ i
~ ~ ~ ~ ~
- REGION OF ACCEPTABLE ~ ~ ~
0.55 OPERATION ~ ~
'I ~
~ ~ ~ ~
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I 0.50 I
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a
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a ~ . )...~ (.30, 0.46)
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z :OPERATION;::: .
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~ ~ ~ ~ ~ ~ ~ ~ ~
0.35 0.30
-0.3 -0.2 -0.1 0.0 0,1 0.2 0.3 CORE AVERAGE ASI SEE SECTION 3.2.7 FOR THE ASI OPERATING LIMITS fIGURE 3.2-2 PNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS 5'COLSS OUT Of SERVICE)
PALO VERDE - UNIT 3/4 2-7
i i
0
FIGURE 3.2-3 REACTOR COOLANT COLD LEG TEMPERATURE vs CORE POWER LEVEL 580 575 570
- u. 570 O 568 568 565 AREA OF ACCEPTABLE cx 560 OP E RATION 562 g 555 Q
552 O 550 8
l0 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL,% OF RATED THERMAL POWER FIGURE 3. 2-3
~~
REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POMER LEVEL PALO VERDE UNIT 2r 3/4 2-10
ib
'FIG UR E 3.3-1 DNBR MARGIN'OPERATING LIMITBASED ON COLSS FOR BOTH CEAC'S INOPERABLE 140
~ ~
C< ~
7'
~ \ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
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120 I ': ~ s (100, 118. 7)
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REGION OF 40 UNACCEPTABLE-OP E RATION 0o 20
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0 20 40 60 80 100 PERCENT OF RATED THERMAL POWER PALO VERGE - UNIT E 3/4 3-10
II 0
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30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE E UIVALENT I-131 .PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POMER MITH THE PRIMARY COOLANT SPECIFIC ACTIVITY > 1.0 Ci/GRAM DOSE E UIVALENT I-131 PALO VERQE - UNIT iree'/4 4-28
0 F I G URK 2 44 RCS P R ESS/TEMP ILBNPJS 0-19 VBR.
3000 2500
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.. HEATUP
- 5 100/HR COO LDOWN
~ ~ ~ l ~
i '-i "l I 1 i 100 200 Egg 420
.,)NDICATED RMP.11 (Pgj) FIGURE 3/g 3L@-g RCS PRESS/TEMP,LIMI!TS (0 - 'l5 Mg ~ pggpg.i~~~g PALO VERDE - UNIT .3/4 4I-Z)
Ik 8 REJECT Q. G CONT.I N NE TESTI N 6
@. ~
0 10 20 '0 40 50'$ V8 $8 90 I 00 FIGURE 4.7-1 SAt1PLING PLAN FOR SNUBBER FUNCTliBHRL Ilk~i PALO VERDE - UNIT $ 3/4 7-26
II ik 0
Transition Temperature Shift 'F 200 ( m Kl C7 m 150 100 0 hb Q I C) o~ 00 CIO 101 10 10 NEUTRON FLUENCE 0 A5338 CL 1 PLATE 0 WELD METAL FIGURE B 3/4.4-1 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E > 1 MeV) NEUTRON FLUENCE (550 F IRRADIATION)
'LVINTERSBURG ROAD
~
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'r i"r Qqt UNIT 1 HET UNIT 2 TOWER UNIT 3
~ 4
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LEGEND ELLIOT ROAD CENTERLINE'OF CONTAINMENT (V/ARD ROAD) PROPERTY PURCHASED EXCLUSION BOUNDARY SITE BOUNDARY NQA TH PROPFRTY PURCHASED r//rr.. OUTSIDE EXCLUSION AREA 0 SI TE 'At<D EXCLUSIGH SOU)'CEDAR I Eg SCALE t'ai)ifgi) I"IGURE 5.1-1 5-2' PALO VERDE U"IIT
, ~
0 il J 0
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~r LOW POPULATION ZONE PALO VERDE NUCLEAR GENERATING STATION FIGURE 5 1-2 PALO VERDE - UNIT% 5-3'
II ll'l 0
CEO EXECUTIVE V.P. OIR. PROJECT SERVICES V.P. NUCLEAR PRODUCTION PIR, CORPORATE PA HGR. NUCLEAR SAFETY ISEG/NSG ASST. V.P. NUCLEAR PROOUCTION HGR. PROJECT. CONTROLS ASST. HGR CORPORATE PA l ONSITE HGR. AOHIN. SERVICES PVNGS TRANSITION OIR. TECHNICAL SERVICES l PLANT MANAGER MGR. EHPLOYEE RELATIONS I HGR. OPERATIONS f
/ HGR. NUCLEAR ENGINEERING I
HGR. PUAI.ITY SYSTEHS/ ENGINEERING HGR. PROCUREHENT PUALITY HGR. CONTRACTS HGR. MAINTENANCE HGR. NUCLEAR CONSTRUCTION C PURCHASING HGR. PUALITY AUOITS/ MONITORING MGR. OUTAGE HGR. RECOROS MGR. PARTICIPANT SERVICES MANAGEMENT ONSITE HGR. PUALITY CONTROL HGR. PLANT SERVICES HGR. NUCLEAR FUELS HGR. EHERGENCY PLANNING ON SITE HGR. LICENSING FIGURE 6.2-1 OFFS I TE ORGANI ZATION
1i il' Cl
TABLE 3.'3 5 (C~~'ltfNÃgQ ENGINEERED SAFETY FEATURES RESPMBE 7KNES INITIATING SIGNAL .AND FUNCTION !Pemmax ~<<,Z Cm SZCONDS
- 8. Steam Generator Level - High
- a. Main Steam Isolation
- 1. MSIS actuated MSIV's R.S"-/i%i..6"~
- 2. . MSIS actuated MFIV's¹ M.s //~5JP
- 9. Steam Generator hP-High-Coincident 'Qith: Mani Kemrrathw Eavelt Kaw
- a. Auxiliary Feedwater Isolation 35i //Ilsr from the Ruptured Steam Generrtev
- 10. Control Room Essential Filtration h~a5zorrr 3JMP'~//L89F~'~
- 11. 4.16 kV Emergency Bus Undervo)Cage (Degraded Voltage)
Loss of Power 90K system voltage
- 12. 4.16 kV Emergency Bus Undervoltage gloss mt 9/xPjthgp))
Loss of Power TABLE NOTATIONS Diesel generator starting and, sequence loaÃzg @claps inrrcil~ Response time limit includes movement of valves .and ~imrtmC ~ff guns car Mevter discharge pressure.
"~Diesel generator starting delays not inctu5&l. W7~'i'Lw guar ~va~la'b'.l~.
Response time l.imit includes movement of vailzmr, ~nd adÃm5lrtma& eti pump or. blower discharge pressure.
¹MFIV valves tested at simulated operating cmrmM59mm" wa.lees tt~~ at
-4+VHu-
~
Qcsponhp.
%Rip 0& gAOlA xi~ ~
static flow conditions to 8.6/8.6 Qwb~W<M.,MOA~s ~ ~~~~M seconds. l<N gy ~+ ~flCWM~Q 2LTL X<A< )~~~~~s
~ ~
~z 5Qg-Q<- So
~~~gugyAC'&5
~~i+ ~+ ~ +~A'n+ ~->~ ~ -,~gg gn,-'~~~~g
~, A PALO VERDE - UNIT 2 3/4 3-.29
il 0
INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 ws a minimum, the fire detection instrumentation for each FPER detection zone shown in Table 3.3-11 shall be OPERABLE. APPLICABILITY: Mhenever equipment protected by the fire detection instrument is required to be OPERABLE. ACTION:
- a. With any, but not more than one-half the total in any fire zone Function X .fire detection instrument shown in Table 3.3-11 inoperable, restore the inoperable instrument(s) to OPERABLE status within 14 days or within the next 1 hour establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours or monitor the containment air temperature at least once per hour at 6 aP the locations listed in Specification 4.6. 1..5.
- b. With more than one-half of the Function X fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Function Y fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour establish a fire watch patrol.
to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5. 8oP= C. The provisie6s of Specifications 3.0.3 and 3.0.4 are not applicable. 'SURVEILLANCE RE UIREMENTS 4.3.3.7. 1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAl TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTOOMN exceeding 24 hours unless performed in the previous 6 months. 4.3.3.7.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. PALO VERDE - UNIT 2 3/4 3-6O
0 Cl
TABLE 3. 3-13 (Continued) TABLE NOTATION "" At all times. During GASEOUS RADWASTE SYSTEM operation. 0 During waste gas release. N 'n MO ES 1, 2, 3, and 4 or when irradia""d fuel is in the fuel storage pool. ACTION 35- With the number of channels O."EP/'.BLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release: a0 At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of. the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 36- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION,37- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of (A) or (B) are performed:
- a. Initiate the Preplanned Alternate Sampling Program of Specification 6.16 to monitor the appropriate parameter(s).
- b. Place moveable air monitors in-line or take grab samples at 'least once per 12 hours.
ACTION 38 " With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. ACTION 39- With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the GASEOUS RADWASTE SYSTEM may continue provided grab samples are taken and analyzed daily. With both channels inoperable operation may continue provided grab samples are taken and analyzed (1) every 4 hours during degassing operations, and
- (2) daily during other operations.
PALO YERDE - UNIT 2 3/4 3-74
0 ik 0
G S. wl Cast HOWVOVWE OATE SUBJECT SWEET No. CHECKED BY DATE JOB NO. Action 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the following action of (A) or (B) are performed:
- a. Place movable air monitor in-line
- b. Take grab samples at the mode specific frequencies indicate below.
Monitor Mode 6 5 4 3 2 1 RU-141 N/A iV/A D D S S RU-143 M M D D S S RU-145' M M M M M Vent shall be sampled daily while moving irradiated fuel.
II ~O
TABLE 4.6-1 TENOON 'SURVEILLANCE -,FIRST YEAR Tendon Visual Monitor Oetension Remove Test No. Inspection Forces Tendon Mire Mire V43
+ Ha No
'No, No No No No X
+'o ~ No pP'~ .~ ADo V62
(,A') V75~ H13-007<
~ X X
X 4 ga Qb A( ~ < Po )do H13-021 X + go No No No H21" 037 X ,+Ho No No ,No H21-044 X + go No No No H32"016 X + g~ No No No Q) H32-030' P'3o Notes:
"X" means the tendon shown shall be inspected for the stated requirements during this surveillance.
- 2. "A" means the tendon shown shall be inspected for the 'stated requirements during 'the next or second surveil.lance.
- 3. "No" 'means that inspection is not required for tha't tendon.
- 4. """ means control tendon.
PALO VEROE - UNIT 2 3/4 6-12
, ~,
0
CONTAINMENT SYSTEMS 3/4.6. 2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM h LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with earth spray system capable of taking suction from the RMT on a containment spray actuation signal and automatically transferring suction to the containment sump on a recirculation actuation signal. Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger. APPLICABILITY: MODES 1, 2, 3, and 4." ACTION Mith one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the inoperable spray system to OPERABLE status within the next 48 hours or be in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE RE UIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE: a0 At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is positioned to take suction from the RMT on a containment spray actuation (CSAS) test signal.
- b. By verifying that each pump develops an indicated differential pressure of greater than or equal to 27 psid at greater than or equal the minimum allowable recirculation flowrate when tested pursuant to Specification 4.0.5.
C. At least once per 31 days by verifying that the system pipirg is full .of water to the 60 inch level in the containment spray header (>115 foot level)..
- d. At least once per 18 months, during shutdown, by:
- l. Verifying'that each automatic valve in the flow path actuates to its correct position on a containment spray actuation (CSAS) and recirculation actuation (RAS} test signal.
- 2. Verifying that upon a recirculation actuation test signal,
.the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.
"Only when shutdown, cooling 'is not in operation. PALO VERDE UNIT 2 3/4 6-15
'I II 0
PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-4 shalll he. QHERNBLE APPLICABILITY: Whenever equipment in the areas protected hyg tUim fives hose stations is required to be OPERABLE, except that fire hose s~ixna ligated in containment sha3-1 .have their containment isolation valves claret firn SIDES 3., 2, 3, 4, and 5'CTION: ao With one or more of the fire hose stations shown %nt liakTk 3.7W inoperable, provide a gated wye on the nearest OPSTtML~Z: ihjse sation. One outlet of the wye shall. be connected to the stfarrdhndf Tfxegfh ef hose provided for the OPERABLE hose station. The sanazdl mC'ice of the wye shall be connected to a length of hose suIi5TKcti~ M ymvide coverage for the area left unprotected by the incqamaDille. Hest s+tion. The above action shall be accomplished within one Nmn'ift'%a >aoper-able fire hose is the primary means of fire supprsasnlarn;; eCtmwise provide the additional hose in 24 hours. The hose for the unprotected area shall be stored.ak N8.OMBRE hose station. Signs identifying the purpose. and 1ama@iiom eT Cibe fire hose and related valves shall be mounted above the Heaei andi at, the inoperable hose station.
- b. The provisions of Specifications 3.0.3 and 3.Q.4 hei no%; agyliiic Me.
SURVEILLANCE RE UIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7W) sfiaiH!ba demonstrated OPERABLE: a0 At least once per 31 days by visual inspection of ti.'ie ~axns accessible during plant operation to assure all re@mnm5 eqntlIpment is at the station.
- b. At least once per 18 months by:
Visual inspection of the stations 'not accessiblle dluriirng ip3ant operations to assure l,'I all required equipment is altt Chs ~Coon.
- 2. Removing the hose for inspection and rerackinL, ag4
- 3. Inspecting all gaskets and replacing any degrMhdl aparkeM in the couplings.
"If ~
t 1s to be performed in containment during MODE 5 %m !hre hose stations located in containment shall have their contains@ ho'+worq -< . PALO VERDE UNIT 2 3/4 7"37
I il il I I il
TABLE 3.7-5 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HERE JFKMK LOCATION .HRBAWi'MISBER 150'lant North of Fuel Bldg. 100'lant Mest of Rad !he+a Rldg.- 150'lant Northwest of, F!!ol Bldg. "No hose house, however, the hose station is used to service ~undam~M transfer pump PALO VERDE - UNIT 2 3/4 7-41
0 il
TABLE B 3/4.4-1
<774- oI REACTOR VESSEL TOUGHNESS F-71)- o L
~(FORGINGS F'-77<- o >
F-7~v-o4 DROP TEHPERATURE OF MINIMUM UPPER
'7Q 7-ol WEIGHT CHARPY V-NOTCH~ SHELF C ENERGY P-]4 1-o E RESULTS RT NDT(b) 30 ft- lb ft-ta I 50 FOR LONGITUDINAL PIECE NO. CODE NO. MATERIAL VESSEL LOCATION ~Of } ~('F lb DIRECTION-ft lb 128-101 H-6703=1 508-CLED In'let Nozzle -20 g-gO +20 +60 N.A.
128-101 128-101 H-6703-2 H-6703-3 SA SA SA 508-CLg9 508-CL2'3 Inlet Inlet Nozzle Nozzle 30 Qo M W
+K.go C~ QQ
-25
-27 '
+10
+18 N.A.
N.A. 128-101 H-6703-4 SA 508-CLED Inlet Nozzle -9o A e-qo +5 +42 N.A. 131-102 M-4307-1 SA 508-CL2'I Outlet Nozzle Safe End ~-3a 4R lQ +30 +68 N.A. 131-102 ~ M-4307-2 SA 508-CLZl Outlet Nozzle Safe End W-30 +8-]o +30 +68 N.A. 08-4 ~~i.508-CL2 ~mB~~t~sio~~ WL%~Wet-}}ozr1e-Extenso~~ 128"301 H-4 -1 SA Outlet Nozzle -10 35}((* 10}}(* N.A. 12&-301 !1-4304-2 SA 508-CL2 Outlet Noizl e "10 3 5*}}'10 10}}(}}( N.A. 131-101 H-6712-1 SA 508-CLl Inlet Nozzle Safe End -10 +45 N.A. 131-101 H-6712-2 SA 508-CLl Inlet Nozzle Safe End ~O +10 +45 N.A. 131-101 H-6712-3 SA 508-CLl Inlet Nozzle Safe End +7 +50 N.A. 131-101 126-101 H-6712-4 M-6705-1 SA 50&-CLl Inlet Nozzle Safe End Z 90 80 -78
+7 +5U "28 N.A.
N.A. SA 508-CL2 Vessel Flange 106-101 M-6706-1 SA 598-CL2 Closure Head Flange So "80 "54 N.A. N.A. = Not Applicable (no minimum upper shelf requirement). Lower bound curve valves. "* = Average of three test results. (a) = Determined per applicable ASME-BPV-Co'de Sect.
=
III, Subsection NB, Article NB-2331-(a-1,2,3). (b) 0 and 180 specimens had the same values. g le-ol F. le-O'K F-IL t -0'l
- g. tl+eZ F-'4 lo-o'5 F'-'l4s.o t
<- ave,- L F-1 4L-+'L
~ i Ik il 0
TABLE B 3/4.4<<1 (Continued). REACTOR VESSEL TOUGHNESS (PLATES) DROP TEMPERATURE OF MINIMUM UPPER MEIGHT RT (a) CHARPY V-NOTCH" SHELF C ENERGY RESULTS NDT. 8 30 8 50 . FOR LONGITUDINAL ~ PIECE NO. CODE NO. MATERIAL VESSEL LOCATION ~F ~(rF ft - 1b ft - 1b DIRECTION-ft 1b 142-102 "4311- SA 533-GRB-CL1 Lower Shell Plate ~- (o ~ lo "6 +40 JoS 142-102 H 4311 SA 533-GRB-CL1 Lower Shell Plate <<gf <<g'g 0 "24 "8 127 142-102 H- 1 -3 SA 533-GRB<<CLl Lower Shell Plate -8f-4o A-Qo "7 . +14 %4& /gf 124-102 H-6 l-l Intermed. Shell Plate Bo +W -Ko +44 +90 ea 124-102 124-102 H-6 1-2 H- -3 SA SA SA 533-GRB-CL1 533-GRB-CL1 533-GRB"CL1 Intermed. Shell Plate Intermed. Shell Plate
-Sf'-zo "30
+AS lO JQ +56
+39
+98
+89
))q 9& (g)
H- 70 -4 533-GRB-CLl Upper Shell Plate "30 122-102 122-102 122"102
.H 701 5 H 6701-SA SA SA 533-GRB-CL1 Upper Shell Plate 533-GRB-CL1 Upper Shell Plate -30 fp ~ le
+$ 8 cR
+~ o
+82
+49
+42
+120
+98
+96 N.A.
N.A. N.A. 102<<102PC H 6709- . SA 533-GRB"CLl Closure Head Dome W-4o +36 . +66 N.A. 102<<1029 H 6709-2 SA 533-GRB"CL1 Closure Head Dome -K-su W-Qp +4 +37 N.A. . 150-102 H-6715-1 SA 533-GRB-CL1 Bottom Head Dome 25-9p $0 +2 +30 N.A. 150-102 H-6715-2 SA 533-GRB-CLl Bottom Head Dome -AtLgp +26 +50 N.A. (a) = Determined per applicable ASHE-BPV-Code Sect.
=
III, Subsection NB, Article NB-2331-(a-1,2,3). N.A. Not Applicable (no minimum upper shelf requirement).
= Lower bound curve values of transverse specimens.
C-Y73-ol F'q1> oZ, f I f$-05 F'- l4b=o~( p-14$ -ob fr-z~f'ol l lp'f.oLr 5=)AD 8'-oX P lM.o3 5= 770-o I F-1aoeZ f-Tl) -O1 4= 71<-o2
0 43 TABLE 3.3=3 (Continued) ENGINEERED SAFETY FEATURES ACTUATIOH SYSTEM INSTRUMENTATION MINIMUfi TOTAL HO.'. CHANNELS CHANNELS APPLICABLE ESFA SYSTEM FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION YI. AUXILIARY FEEDWATER (SG-l)(AFAS-1) (Continued) B. ESFA System Logic
- 1. Matrix Logic 6 1 2 3 17
- 2. Initiation Logic 4(c) 2(d) 1, 2, 3, 4
- 3. Manual AFAS 4(c) 2(d} 1, 2, 3, 4 15 r-.. ~
C. Automatic Actuation Logic 1 '1,2,3,4 16 C VII. AUXILIARY FEEDWATER (SG-2)(AFAS-2) A. Sensor/Trip Units
- 1. Steam Generator 82 Level- Dl3 Low 1 2 3 13+ 1 4J(
g s
- 2. Steam Generator b, Pressure - SGl > SG2 1 2 3 13", 14" ~i a B. ESFA System Logic
- 1. Matrix Logic 1,2,3 17
- 2. Initiation Logic 4(c) 2(d) 1, 2, 3, 4 12
- 3. Manual AFAS 4(c) ~
2(d) 1, 2, 3, 4 C. Automatic Actuation Logic 1 1, 2, 3, 4 16 VIII. LOSS OF POWER (LOV) A. B.
- 4. 16 kV Emergency Bus Under-voltage (Loss of Voltage)
- 4. 16 kY Emergency Bus Under-voltage (Degraded Voltage) 4/Bus 4/Bus 2/Bus 2/Bus P
3/Bus 3/Bus 1 1'2 2 3 3 h'513K'4K 13*, 14* CONTROL ROOM ESSENTIAL 'FILTRATION 2 1 All Mode 1QA Q'X.
CD)~1'TROD '::-9 8"f US:~P. TABLE 3. 3-3 (Continued) TABLE NOTATIONS (a) In MODES 3-6, the value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer pressure and this value is maintained at less than or equa e ual to.400 p si*; th e setpoint, shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia. (b) In MODES 3-6, the value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached. (c) Four channels provided, arranged in a selective two-out-of-four configuration (i.e., one-out-of-two taken twice). (d) The proper two-out-of-four combination. The provisions of Specification 3.0.4 are not applicable. After the initial criticality of Unit 2 or Unit 3~ ACTION STATEMENTS ACTION 12 - .With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE
. status within 48 hours or be in at least HOT STANDBY within,the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
ACTION 13 - Mith the number of charm'els OPERABLE one less than the Total Number of Channels, STARTUP andlor POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour. If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6. 5. 1. 6. h. The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN. With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below. Process Measurement Circuit
- l. Steam Generator Pressure- Steam Generator Pressure - Low Low Steam Generator Level 1-Low (ESF)
Steam Generator Level 2-Low (ESF)
- 2. Steam Generator Level Steam Generator Level - Low (RPS)
(Wide Range) 'Steam Generator Level 1-Low (ESF} Steam Generator Level 2-Low (ESF) PALO VERDE - 'UNIT 1 3/4 3-23
il 0
'.~.M'J~l J aE'Q:. Q 3 '2 ~J
~J INSTRUMENTATION J'ASES.
REMOTE SHUTDOWN SYSTEM (Continued) The parameters selected to be monitored ensure that (lg 15m czrM5tien of the reactor is known, (2) conditions in the RCS are known, (3) dhole Meam generators are available for residual heat removal, (4) a source of watjea iir awa$ 1jable for makeup to the RCS, and (5) the charging system is available the maMup mat,er to the RCS. The OPERABILITY of the remote shutdown system insures %he; a imam will not preclude achieving safe shutdown. The remote shutdown sp~em %esXv~menta-tion, control and power circuits and disconnect switches neraszmg M e3iminate effects of the fire and allow operation of instrumentation, ean<~lj and power circuits required to achieve and maintain a safe shutdown mmimitixrn ave independent of areas where a fire could damage systems noma>ljljy/ esa8 the reactor. This capability is consistent with General Der>firqp> KmMman 3
~ shutdown and Appendix R to 10 CFR 50.
The alternate disconnect methods or power or control ciinzuIjj5s mneme that sufficient capability is available to permit shutdown and oaCnOanavme ef cold shutdown of the facility by relying on additional operator aetNenrs ~M caecal control stations rather than at the RSP. 3/4. 3. 3. 6 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrune~4l~Mijam ensures that sufficient information is available on selected plant yenama~taa M monitor and assess these variables following an accident. This cap-tbiiljijdpj f>s consistent with the recommendations of Regulatory Guide 1.97, "Instrunandath'ice f'm K.ight-Mater-Cooled, Nuclear Plants to Assess Plant Conditions During andliFn'~l;lawing an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Leanm@j"jjask farce Status Report and Short-Term Recommendati'ons;" P The containment high range area monitors (RU-148 & RU-lj48)) anil <he main steamline radiation monitors (RU-139 A&B and RU-140 A&B) av. ijrn 'T&1in 3.3-6. The high range effluent monitors and samplers (RU-142, RU-if% zmQ RD-3.46) are in Tab~le 3 g-13. The containment hydrogen monitors are in !gxecii&llea-tionC3//4.6.5.1.'he Post Accident Sampling System (RCS coolly ws im Table 3. 3-6.~ The Subcooled Margin Monitor (SMM), the Heat Junction >1h~ernrgcnuple (HJTC), and the Core Exit Thermocouples (CET) comprise the Inadequate Gene Cooling (ICC) ia strumentation required by Item II.F.2 NUREG-0737, the post '7~,jjIit-2 .Action plan. The function of the ICC instrumentation is to enhance the abjj'llij~ ef 'the plant operator to diagnose the approach to existance of, and recook~ Imam ZCC. Additionally, they aid in tracking reactor coolant inventory. Mass instruments are included in the Technical Specifications at the request et lVCC Generic Letter 83-37. These are not required by the-accident analysijs rTn< M bring the plant to Cold Shutdown. PALO VERDE - UNIT 1' 3/4 3-4
4 iP 0
( m
't C7 .00 m
0.90 I 0.80 M Vl IQ f/) lR
~
IA m 0.70 .H C)H M 00 0.60
~
a0 J m C
~ 7t g~ fgesa C) ~ z1 0.50 Po 3 A I', A GI ION 6
I l IR y,g g I m 5 jJ d)30 0 k5 I 6BA Mxvl+RAt)AT = vgmfgg
J 4P l1
F IGUR E 3.1-2B CORE POWER LIMITAFTER CEA DEVIATION% z O
~K
~ LLJ EEE 0 30
~0 20 ~ ~ ~
(60 MIN, 20%%d) O~
.G I ~ I O l- ~ I t
~ O 10 D I- I~
ax UJ LZ: I g CC 0 u QO
~O 0 10 20 30 40 50 60 Z TIME AFTER DEVIATION,MINUTES "WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL.
POWER PER THIS LIMITCURPE, FURTHER REDUCTION IS NOT REQUIRED FIGURE 3. 1-2B CORE POMER LIMIT AFTER CEA DEVIATION~ PALO VEROE UNIT if 3/4 1-24
ll' PANGS PLANT MANAGER OUTAGEHANAGEIIENT TECHHI GAL OPERATIONS HAINTEHAHCE PLANT SERVICES HAtlAGER SUPPORT HAtlAGER HANAGER HANAGER HANAGER HAHAGER HRF SUPERIHTEtlDEtlT SUPERVISOR, ttRF HANAGER TRAINING OPS ENGIIlEERING HAINTENANCE SUPERINTEtiDENT HAtlAGER UNIT I SUPERINTENDENT OPERATIONS SECURITY ICC HAIHTENAllCE SUPERINTENDENT SUPERVISOR HAtlAGER UNIT 2 SUPERINTENOEtlT FIRE PROTECTIOH RAD. PROT. C CHEN. HCC SUPERINTENDEHT SUPERVISOR UNIT 3 SUPERIHTENDENT COHPLIANCE ELEC. HAINTENANCE SUPERVISOR SUPERINTENDENT OPERATIONS SUPPORT SUPERINTENDENT OPS COHPUTER STATION SERVICES SYSTEH SUPERINTENOEHT HECHANICAL HAINTENANCE FIGURE 6.2-2 ONSITE UNIT ORGANIZATION
0 C
r TNIIAO T POINT MAINSILAM SUIYUHT STHUCIUNE ~ CONTAINMENT ULUG AUXILIARYBLDG
~ ~
~ VACUUMPUMP EXHAUST I
TUI(BINE BUILDING FUEL BUILDING E XHAUST POINT FUELBLDG>> Ia GEN RADWASTE BUILDING 'UILDING CONTROL BUILDING 9'.2'IESEL a PL LAUNDRY'ECONTAMINATION FACILITY(UNIT I ONLYI CONT PLAN'T NORTH rI rr r S+
~ ~
I.0" PL CONT'5 112' I2a'.0
- - '246'4" I
I Palu Vaadr Nuakaa Iiaucaaling Slaliw L TYI'ICAL POML'R BIDCK ExoausT poiNTs HEY pLaw IJI I Ira (elevation of exhaust point above grade) Plant Vent Building 145'uel 116'acuum 84'O-I"-86 I I Pump
~7 i. XF C 0, 0}}