IR 05000277/1986004
| ML20199G605 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/10/1986 |
| From: | Hoiwe A, Howe A, Keller R, Kister H, Lange D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20199G598 | List: |
| References | |
| 50-277-86-04, 50-277-86-4, 50-278-86-04, 50-278-86-4, NUDOCS 8606250286 | |
| Download: ML20199G605 (200) | |
Text
{{#Wiki_filter:_- - - _ _ _ _ _ _ _ _ _ .
i U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION AND PARTIAL REQUALIFICATION PROGRAM EVALUATION REPORT N05. 86-04(0L)/86-04(0L) FACILITY DOCKET NOS. 50-277/50-278 FACILITY LICENSE NOS. DPR-44 and DPR-56 LICENSEE: Philadelphia Electric C Market Street Philadelphia, PA 19101 FACILITY: Peach Bottom Units 2 and 3 EXAMINATION DATES: March 10, 1986 - March 13 1986 CHIEF EXAMINER: & @. M Allen G. Howe, Examiner fo-6-8' Date Projects Section IC Reviewed By w ~ ex_ Dave 'Eange 7h ' _Dat6 Lead BWR Reactor ineer Examiner Reviewed By A//o/M Robert 'M. KeTler ~/
~
Date' Chief Pro'e ts Section 1C APPROVED BY: HabryB.(Kjster Date
/Ob
;
Chief, Projects Branch No 1 I SUMMARY: Operator and Senior Operator Replacement License Examinations were ' conducted at Peach Bottom Atomic Power Station from March 10 to March 13, 198 Five (5) Reactor Operators, nine (9) Senior Reactor Operators and three (3) Instructor Certification Candidates were examined. All candidates passed the written and oral examination with the exception of one Reactor Operator candidate who failed the written and oral examination. A partial Requalification Program Evaluation was also conducte l 8606250286 860616 PDR V ADOCK 05000277 PDR l l
._ . -,
:
1 REPORT DETAILS
..
TYPE OF EXAM 5: Replacement EXAM RESULTS: l RO l SRO l Inst. Cert l l Pass / Fail l Pass / Fail l Pass / Fail l l l- l -_l , I l 1 . l l l Written Exam I 4/1 l 9/0 l 3/0 l l l 1 l_ l I l 1 I l l Oral Exam l 4/1 l 9/0 l 3/0 l l 1 l l___ l l l I i l Simulator Exam l NA l NA l NA l l l 1 l l l l 1 1 '
10verall / 1 l 9/0 l 3 / 0- l l 1 I I l l l l l- l CHIEF EXAMINER AT SITE: Allen Howe, NRC, Region I OTHER EXAMINERS: Frank Crescenzo, NRC, Region I Brian Hajek, (NRC Consultant) Gary Sly (NRC Contractor) Robert Turner, NRC Region I Summary of generic strengths or deficiencies noted on oral examinations and discussed at the exit meetin Generic Strengths - Both RO and SRO candidates were familiar with plant equipment location and with location of reference mate rial in the Control Roo Generic Weaknesses - Both R0 and SR0 candidates exhibited weaknesses in their ' ability to use steam tables and to explain the facility requirements for personnel radiation exposure limit . The R0 candidates showed 'a weakness in'their abildty to explain the ip'eration of GEMAC Controllers and to explain the operation of var ous control system r
- - _ . . _ _ _ _ _ _ _ _ - - - - - - - _ - _ - - -
. , 2
3. The SRO candidates were hesitant to implement the Emergency Plan when presented with various
significant transient . Summary of generic strengths or deficiencies noted from grading of written examinations: RO - Strengths, Procedures - Normal, Abnormal, Emergency and Radiological
; Control R0 - Weaknesses, Plant Design and Systems SRO - Strengths - Plant Systems Design, Control and Instrumentatio Procedures - Normal, Abnormal, Emergency and Radiological Control SRO - Weaknesses - Administrative procedure conditions and limitations General Comment On Written Examination Process:
During the examination review process some errors were noted in the facility training manuals which required some answers to be changed and may have caused some confusion during the administration of this written examinatio These errors were brought to the attention of the facility training group and must be corrected prior to the administration of the next scheduled i examinatio . A partial evaluation of the Operator License Requalification Program was conducted during the same period of time as the replacement examination This partial evaluation was performed in accordance with appropriate Inspection and Enforcement Guidelines and involved parallel grading of 20% of the facility prepared written examinations. Overall, grading by the facility was found to be consistent with grading by Operator Licensing. A followup inspection in accordance with appropriate Inspection and Enforcement guidelines will be conducted by Operator Licensing during
- subsequent replacement examination periods.
I Personnel Present at Exit Interview: NRC Personnel Allen Howe - USNRC, Region I i Frank Crescenzo - USNRC, Region I Bob Turner - USNRC, Region I Tom Johnson - USNRC, Senior Resident Inspector _ .- _ __ _ - , , _ -
Facility Personnel S. Wookey - Training Supervisor S. Roberts - Operations Engineer R. Fleischmann - Manager Summary of Comments made at exit meeting: The Chief Examiner noted that the plant appeared clean and well kep The facility staff was thanked for its cooperation during the examination period. The facility was informed that all efforts would be made to return the exam results within 30 days. The date for the next scheduled exam (December 1, 1986) was confirme Generic strengths and weaknesses determined during the oral examinations were discusse The Facility Operations group noted that the SR0 weakness in use of the Emergency plan was determined by the facility during the internal certification exams.
Attachments: Written Examination and Answer Key (RO) Written Examination and Answer Key (SRO) Facility Comments to Written Exams af ter Exam Review NRC Resolution of Facility Comments to Written Exams
.
. - - . - - -. . - _
. .
1 Attachment 3
! Facility Comments to Written Exams After Exam Review ANSWER 7.05 Part B (2):
The 1,000 cps limit on the main stack and Reactor Building vent stack to prevent a 5 percent MPC release is stated in GP-3. However, the reason for
- that limit is not given in that procedure. At the time that limit was placed i in GP-3, the Tech Spec's limit for instantaneous off gas release was 1 MPC.
J In line with that, ON-103 chose 5 percent of MPC (1,000 cps) as the action level for an ALERT. Because these two procedures are so closely related, a candidate should at least get partial credit for referencing the emergency action level for ALERT in ON-10 REFERENCE: ON-103, Rev. O ] Answer 8.07 ' The response to this situation involves an interpretation of Tech. Specs and a choice of two correct actions. The Tech. Specs allow two interpretations for the response to this situation. Note 1 of Table 3.2.C states, "that the SRM's must be operable or tripped in the Startup mode". Note 6 states," that the SRM's are bypassed when IRM's are on range 8 or above" Because the SRM trip logic is bypassed when the IRM's are on range 8 or above, tripping the SRM , channels would have no effect and, therefore, is not required; and should be
{ considered a correct answer as shown on the answer key and as accepted by the
'
Resident NRC Inspector. Tc trip the SRM channel is a conservative action and ensures compliance with the Technical Specifications even if the plant conditions change. A conservative response that also ensures compliance with the Technical Specifications should also be considered a correct answer, and , does not make the other response incorrec Either of the two correct answers should be accepted for this question, or the question should be voided.
, References: Tech Spec Table 3.2.C Note 1 versus the LC0 interpretation
2
.
w -- - - , - w--,wnr a - ,- ~ , . , - -- , - - -- e - , e- rso\. -w me-- 4 -- -w-r-e--ve
ATTACHMENT 4 NRC Resolutions of Comments on Written Examinations The following represents the NRC resolution to those comments made by the facility as a result of the current exam review policy.
Only those comments resulting in significant changes to the master answer key, or were "not accepted" by the NRC, are listed and explained below. Comments made that were insignificant in nature and resolved to the satisfaction of both the examiner and the licensee during the post exam review are not listed, ie: typo errors, relative acceptable terms, minor set point changes.
7.05 b. (2) If candidate considers due to radiation release, full credit will ' be given.
8.07 Accept both answers only if candidate fully justifies his/her decisio i i
,
I
.
G: kTTRC MCDY l
- : , :, -
_
'
u
.
U. S. NUCLEAR REGULATORY COHHISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: PEACH BOTTOM 2&3 _________________________ REACTOR TYPE: BWR-GE4
.________________________
DATE ADMINISTERED: 86/03/10 _________________________ EXAMINER: HAJEK, B. APPLICANT: __ _ INSTRUCTIONS TO APPLICANT: _____--______-____________ Use separate paper for the answer Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will oe picked up six (6) hours after the examination start % OF CATEGORY % OF APPLICANT S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY ________ ______ ___________ ________ ___________________________________ _ 1 __ _ 1_ ___________ ________ PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERh0DYNAh1CSr HEAT TRANSFER AND FLUID FLOW , _ 1 __ _ 1 ___________ ________ PLANT DESIGN INCLUDING SAFETY AND EHERGENCY SYSTEMS 25.00 25.00 ________ ______ ______ __ ________ INSTRUMENTS AND CONTROLS 25.00 25.00 RROCEDURFS - NORMAL, ABNORNAL, ________ ______ .___ ___ _ _____ EMERGENCi AND RADIOLOGICAL CONTROL 100.00 100.00 TOTALS - --_____- _-__-_ ___________ ________
' FINAL GRADE %
All work done on this examination is my own. I have neither given not received ai EPPL5CE T I5~55GUATURE~~~~~~~~~~~~~~ l j
;
. i
. '
l . PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2
--- isENs55isisiEs- REEi iEEssFEE Es5 FEUi5 FE5s ________
_________________________________ QUESTION 1.01 (2.50) A. What is meant by the tern. BETA with regard to reactor theory? (1.0) B. How does an INCREASE in DETA affect the reactor's response to the same positive reactivity addition ? (0.5) C. From BOL to EOL, does the core avera3e beta INCREASE, DECREASE or REMAIN THE SAME? EXPLAIN your answe (1.0) DUESTION 1.02 (1.00) The reactivity worth of-a single control rod will ______,
(For each statement below indicate INCREASE or DECREASE.)
a. If the void content around the rod increase (0.25) b. If, with all rods fully withdrawn, the single rod is fully inserte (0.25) If the moderator temperature decrease (0.25) If Xe-135 concentration around the rod decrease (0.25) GUESTION 1.03 (3.00) Following a normal reduction in power from 90% to 70% with recirculation flow, HOW will each of the following change (increase, decrease, or remain the same) AND WHY: The pressure difference between the reactor and the turbine steam ches (1.0) Condensate depression at the exit of the condenser. (1.0) Final Feedwater temperatur (1.0)
(xxxxx CATEGDRY 01 CONTINUED ON HEXT'PAGE xxxxx)
i
. . . PRINCIPLES OF' NUCLEAR-POWER PLANT OPERATION, -PAGE 3 --~~isiss557sisiCi- sisi isisiFEE Es5 FEUi5 FEBs
____________________________________________
.
QUESTION 1.04 (3.00) The reactor scrams at 0700 after 3000 hours at 100% powe In order to meet commitments to the grid, the operations manager desires that the reactor be immediately restarte What are your considerations (relative to time and critical roo density) regarding poisons in the core if the reactor is brought critical during the afternoon of the same day? (1.0) What will occur to the rod density over the next 24 hours after the startup? (0.5) Why is the caution necessary in GP-2, Normal Plant Startup, regarding the potential high uorth of edge rods? What causes these rods to have high worth under these operating conditions? (1.5) GUESTION 1.05 (3.00) List three (3) factors that cause excess reactivity of the core to decrease over cycle lif (1.5) List three (3) factors that will cause Shutdown Margin (SDh) to increas (1.5)
- GUESTION 1.06 (3.00)
A fuel pin, over a period of time, has a uniform coating of corrosion products about 0.001 inches thick on its
- surfac Assuming that power generation within the fuel i pin REMAINS CONSTANT during the time of the buildup,
would you expect the following temperatures to increase, decrease, or remain the same during the buildup? EXPLAIN EACH ANSWE Fuel temperatur (1.0) , Cladding temperatur (1.0) Coolant temperature surrounding'the lower portion of the fuel pin (prior to the onset of boiling). (1.0) i I l j (***** CATEGORY 01~ CONTINUED ON NEXT PAGE xxxxx) l l l I l l
- - . - - - - . - _ - - . _ - - _,, , _ _ _ _ _ . , _ _ _ .__.,,___m.___- --__ -. , ~ , . _,. .___m
__
. . .
PRINCIPLES OF NUCLEAR POWER PLANT 0PERATION, -PAGE 4 isEEE55isEsiCi- siEi iEEssFEE Es5 FEUi5 FE5s ____________________________________________
,
DUESTION 1.07 (2.50) What are the three peaking factors which make up TPF? (1 0) What is the significance of TPF(max)? That is, how is it determined, and what does it mean? (0.75) Given TPF(max), which thermal limit can be verified to be within specifications? (0.75) i
! GUESTION 1.09 (3.00)
Assume the reactor is operating at 100% power and one recirculation pump trips. Indicate how each listed indicated parameter would initially change (INCREASE OR DECREASE) and briefly explain WHY? a. Reactor Power (1.0) b. Reactor Water Level (1.0) c. Feedwater Flow Rate (1.0) GUESTION 1.09 (1.00) Because of a temporarv failure of the process computer, you need to perform a heat balance manually. What are four of the five energy inputs that you would need to use in the heat balance? QUESTION 1.10 (2.00)
, Ouring a loss of coolant accident or loss of feedwater accident there are four (4) basic conditions or actions that must be satisfied or accomplished to MITIGATE the possibility of degraded CORE conditions. 'What are these conditions? (NOTE * Your answer should be limited.to BASIC CbHDITIONS necessary to mitigate the possibility of degraded CORE conditions.) (2.00)
y,) w w.,j-iwMy b he4 fda .d*] pus A '
(xxxxx CATEGORY 01 CONTINUED ON NEXT PAGE.xxxxx)
,. ,_ _ . , _ _ _ . . - _ . _ _ _ . . . _ . . _ . - _ - . _ -
_ ._,
_ _ _ ___
. .
i
'
PRINCIPLES OF.-NUCLEAR- POWER PLANT OPERATION, C' -PAGE Vs
- ~ ~~~~TE5RR557sARICs; REAT TRAssFER E 6'_ FLU 56~EL5U
__________________ = _________ _________
[ , GUESTION 1.11 (1.00)
For each of the following conditions, state how CRITICAL 1 POWER will change (INCREASE'OR DECREASE): Inlet Suce'oling c Increase (0.25) Local Power Increase (0.25) , b.
' Mass Flou Rate Increase (0.25) Pressure Increase (0.25)
;
,
,
,
'
. d I
'
i L
!
;
(***** END-OF CATEGORY 01 *****) t i
L I
! !
I
,
l __ __. _ _ _ , . _ _ _ . _ . . . . . . . _ _ , _ _ _ . _ . . . - . _.- -
.
s
. PLANT DESIGH INCLUDING SAFETY AND EMERGEt4CY SYSTEMS 's1PAGE .6
_ _ OUESTION 2.01 (2.00) The Turbine Building Closed Cooling Water System [Le provides cooling for essential load If the running pump trips on overcurrent, what will cause the standby pump to star (1.00) If the standby pump fails to start, what action should occur to provide cooling to the air compressors and CRD pumps?
(1.00)
NOTE: Include set points snd/or time requirements, if applicabl GUESTION 2.02 (2.00) The 125/250 VDC battery system supplies 250 VDC to various pumps and valves in safeguards system The 3B Charger (which supplies power to the HPCI system) fails. Repairs will take 24 hour Will the HPCI system be capable of auto initiation ouring this entire period? FULLY EXPLAIN (OUR Ar4SWE (1 5) As soon as the charger is replaced or repaired, it is to oe returned to service in the Equalize mod Will the charger voltage read 125, 126, 135, 250, 25o, or 270 volts? (0.5) imm**m CATEGORY 02 CONTINUED ON NEXT :PAGE mummm)
. . PL ANT ~ DESIGN INCLUDING S AFETY AND EMERGENCY' SYSTEMS 'PAGE 7 -------------------------------------------------------
DUESTION 2.03 (3.00) For each of the HPCI (High Pressure Coolant Injection) System component failures listed below, STATE WHETHER OR NOT HPCI WILL AUTO INJECT into the reactor vessel. IF IT WILL NOT INJECT, WHY, AND IF IT WILL INJECT, provide ONE POTENTIAL ADVERSE EFFECT OR CONSEQUENCE of system operation with the failed componen Assume NO OPERATOR ACTION, and that the component is in the failed condition at the time HPCI receives the auto initiation f signa y o Ui The GLAND SEAL EXHAUSTER VACUUM PUMP fails to ;/, operat (1.0) . p_ ./ The HINIMUM FLOW UALUE fails to auto open (stays
#e' h}
A' ,fP cg
-
shut) when system conditions require it to be open.(1.0) Av The HPCI pump DISCHARGE FLOW ELEMENT output signal to the HPCI flow controller is failed at its manimum outpu (1.0) GUESTION 2.04 (2.50) The Compressed Air System includes three compressors which are operated with a? Instrument Air subsystem as the preferred sub-system Consider a compressor lineup with the A compressor in Run, B secured in Automatic, and C serving the Service Air system only. Normal " Instrument Air pressure is 110 psi As pressure drops, at what Instrument Air pressure will the A compressor be fully loaded? (0.25) As pressure continues to drop, at what pressure will the B compressor start and load? (0.25) If pressure continues to drop, what action is necessary, and at what pressure, to permit the C compressor to supply the Instrument Air System? (0.50) As pressure begins to rise again, what will the unloading sequence be for the three compressors, and uhat is necessary to assure the system is realigned for normal operation? (1.5)
(xxxxx CATEGORY O2 CONTINUED ON HEXT PAGE *****)
. .
' PLANT DESIGN' INCLUDING' SAFETY 1AND.ENERGENCY SYSTEMS PAGE B -------------------------------------------------------
GUESTION 2.05 (2.50) Regarding the Standby Gas Treatment System , Whatarekhtee (3) of the four conditions which will auto initiate the system? Setpoints are require (1.50) Consider Unit 2 & 3 separately. Indicate the ]Sinab,*ikq[g primary and back-up ' FAN' (A, B, or C), and the 'r ssa hf t 4 gv primary and back-up ' FILTER-TRAIN' (A or B) for an I auto initiation signa (1.00))nv.rs-CEj $ps QUESTION 2.06 (2.00) The Reactor Recirculation Pump seal cartridge assemblies consist of two sets of sealing surfaces and breakdown bushing assemblies, and seal pressures are indicated on the Recireviation System panel in the Control Room. FOR PARTS (a) AND (b), select the correct statement from the list of possible s.nswers (1 through 4); Failure of the No. 1 seal assembly at full power operating conditions will result in . . . (1 0) Failure of the No. 2 seal assembly at full power operating conditions will result in . . . (1 0)
(1) An increase in the lower seal chamber pressure from 03h& 'kk, approximately 500 psig ..o approximately 1000 psi . 4 A decrease in the lower seal chamber pressure from ~h 5 f (2) fe approximately 500 psig to approximately 0 psi b d^# (3) An increase in the upper seal chamber pressure from 41o+1^ Ik approximately 500 psis to approximately 1000 psi gp g eJJW (4) A decrease in the upper. seal chamber pressure from , geg*[ d approximately 500 psis to approximately 0 psi '
u (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
- . - _ _ _ _ _ _ , - _ _ _
- -
.
.
.
-PAGE 9 PLANT DESIGN INCLUDING 5AFETY AND' EMERGENCY SYSTEMS
- -------------------
-----= __
GUESTION 2.07 (3.00) List the automatic start signals for the emergency diesel generators. Give setpoints where ~
(1.5)
applicabl . Briefly EXPLAIN the response of the ESW/ECW systems with respect to a oiesel generator automatic start.(1.5) GUESTION 2.08 (3.00) ' While you are performing a full flow test of the A Core , Spray loop, a major leak develops in one loop of the Recirculation System, the reactor pressure quickly
!
decreases to about 500 ps29, and then very slowly continues to decreas Core Spray receives an immediate auto-initiation signa Explain what will happen to (1) the Test Bypass l Valve (h0-26A), (2) the hinimum Flow Valve, and (3) the Discharge Valves (HO-11A and 12A). (1.5) Will Core Spray inject? If not, why? If so, under 4 what conditions? (1.5) I QUESTION 2.09 (3.00) A complete loss of Dryuell Chilled Water system has occurred, What three heat loads are affected? (1.0) Which system is the backup cooling system to the drywell? (0.5) If the backup cooling system also fails to remove the heat from the Drvuell heat loads, what two effects will result? (1.0) What action (s) must be taken within 5 minutes if the backup system fails? (0 5)
(*xxxx CATEGORY 02 CONTINUED ON NEXT PAGE *****)
, i y -._n, . , - - , , , , , , . . . - - - - - , - - - , , . __ r- -- - , , +-c
. - _ . . . . _ . , - - - ._ .- .. . _ _ - . - . . . _
!
.
'
, !
f .
-
i j i
!
! PAGE '10 i > PLANT DESIGN' INCLUDING SAFETY AND EhERGENCY SYSTEMS ! ______________________________- - , t
! j
, ' OUESTION 2.10 (2.00) The Automatic Depressurization System will initiate on f receipt of five input signals. Two of these are level l I^i' -
!
signal If the water level is fluctuating, and falls below i the low level initiation point, then rises to above l
' this point, falls again, and rises again, will ADS l i
4 initiate? If it does initiate, uill the valves close if level rises again? Explain your answe (1.0) j l i What is the purpose of the low level confirmatory set point? (1.0) '
,
I l .j ! i t I i ;
;
i l i 1-
,
! .
I
'
;
^
-
, i
'
i ;
!
- '
' (mmmmm END OF CATEGORY 02 *****)
!
! i i !
!
l l
! ! '
I l 1 f-
!
I d
.
_ _ - . _ . _ _ . _ _ - _ . _ . _ _ _ _ _ . - _ _
.
* . INSTRUMENTS AND CONTROLS PAGE 11
____________________________ QUESTION 3.01 (2.50) Assume the Feedwater Level Control System is being operated in 3-element control using reactor level detector channel 'A'. Reactor power is at 85%, steady stat For each of the instrument or control signal failures , I listed below, STATE HOW REACTOR LEVEL WILL INITIALLY RESPOND t incr ease, decrease, or remains constant) and BRIEFLY EXPLAIN WH't in terms of what is happening in the Level Control System immediately following the failur (FOR EXAMPLE, your answers should include the following detail 'Causes reactor level to decrease due to the Level Control System having a steam flow / feed flow error signal, steam flou < feed flow, resulting in a reduction in the speed of the feed pump turbines.') NOTE: A block diagram of the Feedwater Level Control Systen. is attached for your referenc B PUMP FEEDWATER line FLOW signal FAILS HIG (1.25) LOSS OF CONTROL SIGNAL to B REACTOR FEED PUMP speed controlle (1.25) GUESTION 3.02 (2.00) Regarding the starting sequence for a Reactor Recirculation Pump, If the pump can only be operated at 30 percent speed during a pump start at low reactor power or shutdown, why is it necessary for a 50 percent startup signal to be provided to the controller? (1.0) After pump start, what two interlocks must be satisfied for the pump speed to be increased above minimum? (1.0)
(***** CATEGORY 03'CONTINUEL DN NEXT PAGE *****)
. . - = . ._ _ .. _ - . . - - - - - . _ - . . ' ' .
PAGE 12 ! INSTRUMENTS AND C0tJTROLS 4 QUESTION 3.03 (2 00) $ With the plant operating at 100% power, Recire H/A stations in MANUAL, an electrical fault causes the load 4 . control unit input to the EHC system toJdecrease to 90%.. What will be the response of the following to this
occurence, and why will that response occur? Continue } your. discussion to aproximately ONE MINUTE AFTER THE , FAULT. Assume NO OPERATOR ACTIO (Note: An EllC block diastsm is attached for your reference.)
]. Turb2ne Control Valve Position (1 0)
;
' Turbine Bypass Valve Position (1 0) QUESTION 3.04 (3.00) j Explain how the indicated water level would differ from i the actual water level (higher than. lower than, or the same as actual level or as the normal reading) for the i following abnormal conditions. INCLUDE WHY the level indication will respond in the way you indicat Consider only the Feedwater Control Ran3e level ! indicator ,
- Loss of the density compensation to a Feedwater Control Range indicato (1.5)
{ ' Increased Orvuell temperature as a result of a SMALL LOCA near a Recite pump suction no::l (1.5)
!
GUESTION 3.05 (2 50) For EACH of the following conditions, state whether a scram, half-scram, rod block, or no action is generated.
, For conditions that produce more than-one action, state j the more limiting action (i.e. half-scram is more limiting than a rod block).(MODE SWITCH IN RUN) I RPS bus D shifted from normal to alternate power
'
suppl (0.5) Turbine trip at 20% powe (0.5) APRh flow unit B tails downstal (0.5) Scram discharge volume level is at 35 gallon (0.5) Load reject at 50% powe (0.5) !
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) !
! s
i _ _ _ _ _ _ . , . _
. *
, , I
.
! i INSTRUMENTS AHD CONTROLS PAGE .13 3.
f ---------------------------- GUESTION 3.06 (3.00) Air pressure is normally applied to the Scram Inlet and
,
Exhaust Valves to hold them closed to prevent a reactor ,
'
scram from occurrin If a trip signal is received in I either RPS System A or B, ' signals' are sent to the
Scram Pilot Valves and to the Backup Scram Valves to
'
cause air to be removed from the Scram Inlet Valves.
- Are the Scram Pilot Valves and Backup Scram Valves
, normally energized or normally deenergized? (1.0) j When a trip occurs in either RPS system, what
- occurs at the Scram Pilot Valves and at each Backup Scram Valve to cause them to change state?
Include the logic that precludes a scram if a trip ~ cecurs in only one RPS system (either A or B) (2.0) i
! GUESTION 3.07 (2.00)
i The Rod Block Honitor receives inputs from LPRhs, APRMs, j snd the RMCS. For selection of s centrally located control rod, and for RBH Channel A, discuss which
! signals are used, and how the input s23nals are selected i for Passage to the trip units to assure conservatism.
j De sure to discuss The RBh Averaging and Gain Change Unit, and (1.5) l The Recite Flow Inpu (0.5)
] j GUESTION 3.08 (3.00)
The SRMs will give rod blocks during a reactor startuP+ ' What f our conditions will give rod blocks? (1.0) I These rod blocks will be bypassed if the IRhs meet certain range conditions. What are the a range conditions that will result in ' bypassing each of the four rod blocks listed in your answer to Part a? (2.0) i I
- .
(xxxxx CATEGDRY 03~CONTINUEL DN NEXT'PAGE *****)
i
l
,
k
.. . - .- - - . - -
.
.
~
.
*
4 INSTRUMENTS AND CONTROLS .PAGE .14 .
- -=_______
k QUESTION 3.09 (2.50) State the five AUTOMATIC isolation signals that will cause an MSIV closure if the reactor is operating at full powe Include their setpoint (2.5)
'
GUESTION 3.10 (2.50) An automatic RCIC initiation has occurred. Subsequently,
- RCIC injection was automatically terminated due to high reactor water level, WHAT component in the RCIC system functioned to i terminate the injection? (0.5)
' Assuming no operator action, HOW will RCIC respond to water level' decreasing below the high water isolation setpoint? (0.5)
! If a RCIC f ull flow test had been in progress when
- the automatic initiation signal had been received, hou would the system have responded? (0.5) If, following the initiation, the RCIC turbine had
- tripped on overspeed, CDULD it be reset from the Control Room? (0.5) After the automatic initiation, uhat action is
necessary to allow manual control of RCIC? (0.5) i r
(m**** END OF CATEGORY 03 mama '
i
l
._- ._
l
'
l l
.
PROCEDURES -- NORMAL, . ABNORMAL, EMERGENCY AND - PAGE 15 ~
~~~~Ed656L6556dL d6HTR5L'~~~~~~~~~~~~~~~~~~~~~~~
____________________ QUESTION 4.01 (2.00)
The Trip procedures contain several cautions which ma determine if a specific step should be performe Briefly describe the reason or basis for each of the followin3 two caut2on Do not depressurize the RPV below 100 psig unless motor driven pumps sufficient to maintain RPV water level are running and available for injectio (1.0) Do not initiate drywell sprays unless torus water level is below 18.5 fee (1.0) DUESTION 4.02 (2.00) State the entry conditions for the RPV Control and Containment Control TRIP procedure (2.0) ' QUESTION 4.03 (2.00) According to OT-101, High Drywell Pressure, What are the two Immediate Operator Actions that should be taken if a reactor scram has not yet occurred, and (1.0) , How would you accomplish each of these actions? (1.0) i i QUESTION 4.04 (2.50) Concerning Procedure E-28, Loss of All Power on " Both Units (STATION-BLACKOUT). What are the entry conditions? (1.0) What two systems are used to control vessel level during a station blackout? (1 0) What is the INITIAL method of reactor vessel pressure control? (0 5) ! 1 (***** CATEGORY 04 CONTINUED CH4 NEXT PAGE mamma)
- ,- . - . - _ - . _ - _ - - _ _ - - _ . _ _ - _ . - . - - . - .
_ . _ ___ .. ~ . .__ _ . _ _ __ . _ . . _ _ _ . _
.
I .J
. ;
s
'
.
! ' PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND 'PAGE 16 l ! 1 RADIOLOGICAL-CONTROL i ____________________ I
i OUESTION 4.05 (2.50) . Several cautions in .A, B, and C, Reactor Water I (- Cleanup System Startup, Shutdown, and Return to Service I after Isolation, resPectively, warn about fully opening the F/D bypass valve, MO-7 Explain WHEN this caution must be observed, and 4 WHAT would happen if MO-74 was opened full (1.5) f i Under WHAT conditions is full opening of NO-74 i p e r n.i s s i bl e , and WHY is it permissible under these i conditions? (1.0) ! OUESTION 4.06 (1.50) i Procedure SE-2, CARDOX Injection Into the Cable
!
Spreading Room, requires performance of the two j immediate action steps listed below. Briefly explain i the bases for perforneing each action.
I Runback recite flow to minimum on both unit (1.0) ; Transfer house loads on both unit (0.5) ) l l l
'
l t i ! l
;
i
- (mmmmm CATEGORY 04 CONTINUED ON NEXT PAGE **mma)
i i f
,
i l
-
1
- - - - - - . -- - .-___ -
.
, .
. 4. ' PROCEDURES - NORMAL, AE:N DR M AL, EMERGENCY AND PAGE -17 RADIOLOGICAL CONTROL ____________________ OUESTION 4.07 (3 00) Several actions must be taken as a function of RPV pressure or temperature during a plant startup and heatu For each of the following, give the consequence of not taking the action,'or indicate what might be necessary under the given conditions, as indicated by the item. (Exact wording not required) The head spray valves and shutdown cooling valves n,ust be closed before reaching 75 psis, or __________________.(consequence of no action) (1.0) Turbine seals are to be transferred to nuclear steam when the reactor reaches a nominal 100 psig, unless the seals are badly worn, in which case _____________________.inecessary action) (1 0) Whenever the pressure approaches the current EHC setpoint (as it will at 120, 600 and 920 psis, according to the procedure), verify that pressure is held by observing _________.(necessary action) (1.0) GUESTION 4.08 (3.00) According to OT-106, Condenser Low Vacuum, What Immediate Action (assuming a scram does not occur) should be taken, and for how long should you continue this action? (1.0) Why should you not start the mechanical vacuum pump to help mitigate this situation? Explain two reason ( 2. 0 ) GUESTION 4.09 (1.50) According to ON-106, Stuck Control Rod, what restrictions are placed on the use of continuous and r.otch withdrawal methods for moving the stuck rod? -(1.5)
1 (mmmmm CATEGORY 04' CONTINUED ON NEXT PAGE massa) l l
i
I
__ . . _ _ . ._ _ . _ . _ - . ._ _ _ __ - . _ i .
$ ' ! . .
i PROCEDURE 5 - NORMAL, ABNORMAL, EMERGENCY AND PAGE 18 ,'
,
RADIOLOGICAL CONTROL I
i
- QUESTION 4.10 (2.50)
h One of the immediate actions in SE-1, Plant Shutdown ' From the Emergency Shutdown Panel, requires that Drywell i Instrument Air be placed in service prior to evacuating
'
the main control roo The procedure for performing the
- proper lineup is repeated in the immediate action steps because of the critical nature of this ste Why is Drywell Instrument Air so essential that the procedure requires the detail provided? (1.0) Briefly explain the procedural sequence involved in assurring proper lineu (1.5)
DUESTION 4.11 (2.50)
,
Give five items that operators reporting for duty shall l receive verbal reports on from the previous shift according to A-7. shift Operation (2.5) i
}
i
i
!
i ! i ' , i
! '
(***** END OF CATEGORY 04 mmmmm) (************* END OF EXAMINATION ***************)
J ! ! t ! ,
l !
_ . _ _ _ .
* .
. PRINCIPLES OF' NUCLEAR POWER PLANT OPERATION, :PAGE 19
~ ~ ~~~~5HEEE 65UI55C5I~UEET TRIE5fER d 6~5LU56~iLUU
____________________________________________ ANSWERS -- PEACH BOTTOH 2&3 -86/03/10-HAJEK, B. ANSWER 1 01 (2.50) a. BETA, the delayed neutron fraction, is the fraction of neutrons in the core that were produced by the delayed neutron precursor (1.0) As BETA becomes larger, the period is longer for the same reactivity additio (f;gfr u L . /w > (0.5) c. Decrease (0.25) As Pu-239 production increases (0.25), and U-235 decreases (0.25) the core average will decrease due to Pu-239's Beta being so much smaller (0.25). (1.0) REFERENCE PBAPS LOT 1420 p.5,9. SP ecific Learning Objectives 1, 8, 9, 1 ANSWER 1.02 (1.00) Decrease (0.25) 6. Decrease (0.25) c. Decrease (0.25) d. Increase (0.25) REFERENCE PBAPS LESSON PLAN LOT-1490 Objectives 5, 6, and .ps ANSWER 1.03 (3.00) Decreases [0.253. There is less steam flow, therefore, less pressure drop through the main steam lines [0.75 (1 0) Increases CO.25 With the same amount of cooling water through the condenser and less of a heat load, condensate depression will increase CO.75 (1.0) i
! Decreases IO.253. Less extraction steam from the turbine to heat the feedwater [0.75 (1.0)
l
. - . _ - . - . . _-- - - - - _ _ - . = . . . . .- .
e i
*
l
, i j 4 PRINCIPLES OF NUCLEAR POWER' PLANT OPERATION, PAGE 20
--- isisR557EisiC57 sEIT iEEssFEE EA5 FEUi5 FE5E
____________________________________________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HAJEK, B. K.
) t i i REFERENCE LOT-1270, Objectives 3, 4, 7, and 9
~
Part a.
i Parts b and c. LOT-1190, pg. 16, Objectives 3 and ! ! ANSWER 1.04 (3.00) { Xenon will peak at'its h'ighest reactivity
: approximately 10 hours after the scra [0.53 Thus the reactor will go critical at a lower rod density
' than befor E0.53 The rods will need to be inserted after startup to
) control power. (0.5)
, Xenon production is a function of flux level, CO.53 j and since the highest fluxes are in the center of j the core durin3 reactor operation. the xenon level ! will be highest there during a post scram startup.
' C0 53 The flux will be forced to the outside of the core, increasing the peripheral rod worth. [0.53 l REFERENCE PDAPS LESSON PLAN LOT-1510, Objective 6.
' PBAPS LESSON PLAN LOT-1530 (GP-2), Objective 2.
-
.pa
! , ANSWER 1 05 (3.00) r . Fuel depletion Fission product poison buildup -_ oaupYes 7e $w' l> i#,g#g 4 Plutonium 240 buildup if WW evd (1.5)- i l i (0 5 each)
! . Increase in moderator temperature j
" 2. Decrease in Kexcess/p excess i
'
1 Increase in control rod density l Increase in poison concentration (3 at 0 5 each) (1 5) j - REFERENCE
- LOT-0950 pps. 3, 5-6, Objectives-.1, 2, . 7, and B.
! ! !
1 ! !
. _ ,. - - _.- __. . ,. . - - - , _ . . _._.-_ . - _ _ . - . . . - . . . . - _ . . . . . . . . . - . - . , , - - _ - _ . . .
.__ . .
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 21
. 1.
- --- isEis557sAsits- REEi isissFEE Es5 FEUi5 FE55
____________________________________________ ANSWERS -- PEACH E:0TTOM 263 -86/03/10-HAJEK, B. K.
' ANSWER 1.06 (3.00) i- a. Fuel temperature would increase CO.$53 to get the needed delta T to transfer the heat to the coolant. The corrosion layer will require some delta T across it to transfer heat CO.253 l b. Cladding temperature uould also increase IO.853 because the pin temperature increased and the cladding is nou transferring heat to the corrosion film instead of the coolant.EO.R53 c. Coolant temperature rem' a ins the same CO.553 since it is a function of pressure, which is maintained constant by the EHC system. IO.453 7 REFERENCE PBAPS LOT-1320 Fuel Element Temperature Profile, p.4, 6, 10.
', Specific Learning Objectives 1, 4.
J
i ANSWER 1.07 (2.50) i l APF -AYIAL PEAKING FACTOR (.33)
! RPF - RADIAL PEAKING FACTOR (.33)
LPF - LOCAL PEAKING FACTOR (.33) (1.00) It is the maximum peaking factor in the core found by APFxRPFxlP (0.75) Maximum LHCR - MLHGR n M Ft,pp b %. (0 75) REFERENCE PBAPS LESSON PLAN LOT-1400, PG. 7 Objectives RO/SRO 1 AND 3.
. ANSWER 1.08 (3.00) d DecreaseEO.53 due to increased void content in-the core as flow : decreases. CO.53 Cle. la modeuiV (1.0) IncreaseEO.53 due to incr ease, d voiding in the -core EO.253 and .
'
recite pump no longer taking suction on the annulus.EO.253 (1.0) a c. DecreaseEO.53 due to steam flow decreaseEO.253 and level I increaseCO.253 (1.0) l j a
. - . . . . PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 22 ,
. ~~~ isEEE557sisiCi- Riii iEisiFEE As5 FEUi5 FE5s ____________________________________________ ANSWERS -- PEACH BOTT0H 2&3 -86/03/10-HAJEK, REFERENCE PBAPS LOT-1640 Flow Transients, transparency ti, p. 3
; ANSWER 1.09 (1.00) Feeduater Cleanup Control rod drive water Recire pump heating ; - D :cL : ca;: fe.)1M pr && 3] tl66 =7 M 'l %"' (0.25 each for any four)
REFERENCE PBAPS LESSON PLAN LOT-1300 Objective RO/SRO 3 and 2 ANSWER 1 10 (2.00) 1) Reactor made soberitica (0.50) l 2) Limit reactor pressure Eto prevent Reactor Coolant System boundary degradatio (0.50) 3) Haintain adeouate coolant inventor (0.50) ]
; 4) Provide cooling flow adequate to remove decay heat and stored energ (0.50)
REFERENCE ,
!
l LESSON PLAN LOT-1690,pg. 13, Special Objective 3.
i t l ANSWER 1.11 (1.00) i I a. Increase i b.-I;.cr;;;;14u4NR- , ., c. Increase ) d. Decrease REFERENCE LESSON PLAN-LOT-1360,pss. 7&B. Specific Objective N ,,-, ,- - . - - - - - - . - - -,,- , .. -.-, . - - - -- -
-. - - - - - - - - - - - - _ _ - _ _ _ _ _ _ _ _
l
' . l -
.
. PLANT DESIGN INCLUDING SAFETY AND' EMERGENCY SYSTEMS PAGE 23
--____________
. __________________________________ ---- ANSWERS -- PEACH BOTTOM 2A3 -86/03/10-HAJEK, B. ANSWER 2.01 (2.00) A lou E70 psig3 discharge pressure EO.53 for greater than 20 sec. [0.53 If both pumps are off for greater than 40 see EO.53, solenoid valves EAD2352 and 23543 reposition to allow RBCCW backup. CO.53 REFERENCE l PBAPS LESSON PLAN LOT-0430, ppg. 3 - Objectives 2, + P a,
;
ANSWER 2.02 (2.00) No. CO.53 The batteries will carry the load of j the LOCA systems f or 12 hours (or some reasonable ; ...-+-'- time acceptable) CO.53 if some non-essential loads are shed EO.5 J volts REFERENCE PBAPS LESSON PLAN LOT-0690, ppg. 4, 6-8, and Procedure S.B. Objectives 2, 3, 4, and . Pas i ANSWER 2.03 (3.00) Will inject CO.253. Turbine seal leakage resulting in potential air-borne activity.in the HPCI room CO.75 Will inject E0.253. Pump overheating and seal damage may result during low or no flow conditions E0.75 Will not inject IO.253. Maximum signal from the flow element will cause the controller to keep turbine speed at minimum CO.75 _ . - -
.- ._ _ , . _ --
~ -
GL>csreu 2.ct - pas b .
,
l l
' .
LOT-069D-Page 3 of 12-Rev. 000
- 1 s Subject Outline Support Inform 2 tion $
a) Float 236.5 -
' '
'
279.0 VDO b) Equalize 2%.3 - 288.0 VDC /250 VDC (Safeguard Loads)
- Battery 1) 4 separate batteries
,
(2A, 2B, 2C,2D)
2) Lead-Calcium type
. 3) 33 cells each *
4) Discharge rate @ 190 amps for 3 hours .
- . 5) 2A & 2C Di .
2B & 2D Div.11 l ,
' Battery Chargers 1) 480 VAC input . a) 2BCA E124-T-B b) 2BCB E-224-T-S c) 2BCC E-324-R-B d) 2BCD E-424-W-A 2) Output: 200 Amps @ -
125 VDC a) Float 113.2 - 13 VDC bF*==Hih '128.I"- f44.5 VDC: Batteries are uranged in ,
'
serie ) -individual batteries l supply 125 VDC load l centers j arrangement - ) 2) Series l supplies 250 VDC load I centers
,
i
.
l t
, . - , _ - - - _ , _ , _ , _ _ - - . - _ - - , _ , . , .
. . *
l l l l PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEh5 PAGE 24
-------------------------------------------------------
ANSWERS -- PEACH BOTT0h 2A3 -86/03/10-HAJEd, Ei . 1; . REFERENCE PBAPS LOT 340 p. 5, P&ID H-365, H366. Specific Learning Objective: Purpose ANSWER 2.04 (2.50) t psig } gut 4 si psig g Service Air will isolate automatically Ebv the closing of PCV 24283 (0.25) at 95 ps23 ( 0. 2 5 ) * *Lu k VIW 4W8kd.8 \' The C compressor would be unloaded from the M N *N * Instrument Air system by the opening of PCV 2428 (or) the return to service of the Service Air Syst.e m (0.25) at 97 psig (0.25).
The standby compressor (B) has a seal in contact such that an auto start will ecuse it to operate as if it is in RUN until manually stopped and placed back in AUTD. (0.5) Therefore, both A and B will unload together, first to 50 % at 108 psig, (0.25) and tnen completely at 110 psig. (0.25) REFEFENCE PBAPS LESSON PLAN LOT-0730 ppg. 7 - Obiectives 2, 3, and N T64f5 # fro =Jea. S.H. I.3 -b fW P.A.. CL.P. did ut shm clule alWJ ANSWER 2.05 (2.50) . Resctor uater level O' 2. D/W press 2 psis 3. Rx B3de exhaust 16 mr/hr Refuel floor exhaust 16 mr/hr ,
(any 3 at 0.50 ea.)
l Unit 2: PRIMARY: fan A, t 2ir ^ B/U: fan B, t r a i r- 4 (0.5)~3od M A f Unit 3: PRIhARY: fan C, t r a i r. O B/U: Fan B, Note: On i,nitiation both iso. dampers open so both41.N w
: ... ? (0.5) ogr.g4 trainsarepervic _
REFERENCE ! Lt%o" 7b""] LOT- 0210, REV 0, pg 3,5,7. Specific Learning Objective was doa*a - l Mn L 'is L p J u :-2 -
' ' -=
'
s io,s. A. t"d2. 4 G f-f , pg7 DWeaa .n 4" ""?"
.. a
! PLANT DESIGN INCLUDING 5AFETY AND ENERGENCY SYSTEh5 PAGE 25
ANSWERS -- PEACH E:0TTOM 2&3 -86/03/10-HAJEK, E: . K.
ANSWER 2.06 (2.00)
} } /24l )
REFERENCE PBAPS LESSON PLAN LOT-0030, pp , 14, and Transparancy Objective .pa ANSWER 2.07 i3.00) . Triple low reactor uater level -130' 2. Hign D/W pressure 2 psig 3. Loss of off-site p ow e r ('c d . tu vdv.od )
( 50 eact1) On an auto start of the D/G, rpm, the ESW discharge valve opens ( b lu , at{)255 43 (.5)
A,3 ESW and ECW pumps start after 22 seconds. ( 3 /~-4) (.5) 23 seconds later if the discharge pressure is available from ESW, the ECW pumps sto (.5) REFERENCE LOT-0670, REV 0, pg 3,19. Specific Learning Objectives 2, ) E n) g s.p .n)))
'
fqi % $b~rv3g JY'% Elf l * 5
. N
~C D 2 rw MO497h E6M dktb d 4*##~^
# J d /20
- _ - _ - - - _ _ -
.
-
. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 26 _______________________________________________________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HAJER, ANSWER 2.08 (3 00) The Core Spray system is already operating, in the full flow test mode. Therefore the test bypass valve is open and the min-flow valve is close (1) The test bypass valve IMO-26A3 will close with no dela to.5)
(2) The min-flow valve will open when low flow ..
Cless than 600 gpm] is sensed in the flow (oM44 WM I8 A b#{) element. When E600 3pm3 flow is sensed by the flou element, the min-flow valve close (0.5)
(3) When reactor pressure decreases to 450 psis, the discharge valves h0-12A and MO-11A will be signaled OPEN. (Note that h0-11 has been closed for the test.) (0.5) N (Context of ansuer will be considered.) (0 5)
When reactor pressure decreases to below the Core Spray System pressure, injection to the vessel begins when CS pressure overcomes the check valve setting and/or reactor pressur (1.0) REFERENCE PBAPS LESSON PLAN LOT-0350, Procedure 5.3. Dbjective 4 ANSWER 2.09 (3.00)
(negae-E) Recite motor coolers, DW sumptieboler, and the drywell fan coil units (0.33 each) ^ ^ " ' . RBCCW '(0.5) Drywell pressure uill increasee [ approaching the LOCA setpoin(f [0.53 The reactor recire pump motors will begin to overheat. CO.53 The reactor recire pump must be tripped within 5 minute ' REFERENCE PBAPS LESSON PLAN LOT-0150, ON-113, Loss of RBCC Specific Learning Objectives 1, 4, .
_ . _ _ _ . _-_ . _ - _ - - _ . . _
.
.
)
. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 27 ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HAJEK, B. AMSWER 2.10 (2.00) ADS will not initiate until the low level initiation point has been held for at least 105 sec. (0.5) After this,'if it does initiate, the initiation signal will seal in. (0.5) The low level confirmatory signal prevents inadvertent initiation following a single level instron ent f ailur REFERENCE PBAPS LESSON PLAN LOT-0330, pg.5 and T 4 )
Ob iectives 1 and g , .gs '), hr:
-
%; ele l~ 4^ 9 "Ju ' os JJ
.
;-
A od m ___3 y un , ,, k
,
k W4
,
,Y'Ygj,s
-
yd3 3,y mS 1st Y&~ ,,,og *
*} &) n2.r.tY4 ~ 4 w N s' & 1 *
uY Q/ oc yy%.tv. A' m , .ts /+ 4e Tk t w' g sj t s.' r t.+g 1'
.
,
. . ,
, {$ht)lP g9 6Ft-x4Oe)' *
'
C
. . - . .-- . < .
, . INSTRUMENTS AND CONTROLS PAGE 28 ____________________________ ANSWERS -- PEACH BOTTOM 283 -86/03/10-HAJEK, D. K.
, ANSWER 3.01 (2.50) Causes reactor level to DECREASE E0.25] due to the Level Control System having a STEAM FLOW / FEED FLOW ERROR, STEAM FLOW < FEED FLOW E0.53 resulting in a DECREASE IN THE SPEED OF THE REACTOR FEED PUMP TURBINES CO.5 Reactor level should REhAIN CONSTANT CO.253 because the TURBINE SPEED CONTROLLER WILL LOCK CO.53 the ifyN"Q .. # I'*.N reactor feed pump speed at the SPEED LEVEL DEMAr4DED . 0t+ Lo b N AT THE INSTANT PRIOR TO THE SIGNAL LOSS CO.53 ,
t REFERENCE PBAPS LOT-550 Feedwater Control System, , 194 Objective .pa ANSWER 3.02 (2.00) At minimum speedr the torque developed by the motor is not high enough to start the pump The discharge valve must be open (0.5) and the feedwater flow most be greater than 20 percent (0.5) REFERENCE FBAPS LESSON PLAN LOT-0030, ppg. 21 - 2 Objectives 5 and ANSWER 3.03 (2.00) The TCVs will close 10% E0.53 due to the load selector signal decreasing by 10% and being less than the pressure signal EO.5 The BPUs will open by 10% E0.53 due to the throttle pressure. increase that occurs when the TCVs shut E0.53 REFERENCE PBAPS LOT 0590, EHC Logic p. 11-1 Specific Learning Objective: _ - , - - . . -. - _-
. __ - -
~- . _ _ - - - _ _ _ _ . . _-. _ _ _ - -- _ . . . .
.
.
s i, .
PAGE 29 , INSTRUMENTS AND CONTROLS , ____________________________ ' ANSWERS -- PEACH BOTTON 2&3 -86/03/10-HAJEK, B. H.
- ANSWER 3.04 (3.00)
i Indicated level would decrease. CO.53 This is because the density of the reference leg water is i greater than the reactor water, and a milliamp i signal proportional to reactor pressure is added to the dP signal to compensate for the differenc Loss of compensation will result in a lower level indication. C1.03 l Indicated level will increase Eby up to a max of about 12*. CO.5] - This is due to the increase in the reference leg temperature as the Drywell temperature increases and the reactor temperature and pressure remain i approximately constant. E1.03
, '
I REFERENCE PBAPS LESSON PLAN LOT-0050, pp , 7r 17 - 20.
' Objectives 2 and 6.
1 ANSWER 3.05 (2.50)
, half-scram
- no action i rod blockQ b h C'l% % bMh ( A el* O rod block scram l
REFERENCE PBAPS LOT-0300 RPS LP . ,11,12.
, Objective PBAPS LOT-0270'APRM LP p. 64 -Objective PBAPS LOT-0070 CRDH LP p. 18. Objective 5.
l ) h ! !
d ,
, ,,_,y -_ -- _ , - . _ . _ _ _ . _ _ . , - _ v _ - _ , , ,. , , - . _ , , . . . - - . . - . - .
. - . - . . . .
l INSTRuhENTS AND CONTROLS PAGE 30 ____________________________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HAJEK, B. ANSWER 3.06 (3.00) I i Scram pilot valves are normally energize , Backup scrsa valves are normally deenergize Scram Pilot Valves - Each trip system controls one solenoid - one changes state on loss of signal from RPS At and the other on loss of signal from RPS CO.53 Both must be tripped to cause the air header to be vented. E0.53 i Backup Scram Valves - tiust receive signals f rom Luf.c optssed - both RPS A and B to energin CO.5] If either backup scram valve is energized, the air header (
( q g%g g y will be vented. CO.5J J U* E (*, *
,
* * ^
<
kna ,xuv , is wnu[ O REFERENCE i PBAPS LESSON PLAN LDT-0300, ppg. 2-6, and T 4 Objectives 1, 3r and ANSWER 3.07 (2.00) The RBM receives inputs from the four LPRM strings
- Elevels A and C3 around the selected control ro (0.3)
It also receives a core average input frca a , reference APRM EAPRM E, Alternate C3. (0.3) If the LPRM average is less than the APRH signal,
'the LPRh signal is adjusted to equal the APRM signal. (0.45)
i If the LPRM average is eo,ual~to or greater-than the APRh signal, the LPRH average is passe ;(0.45) l , l RBH A receives input from Flow Channel (0.5) REFERENCE PBAPS LESSON PLAN LOT-0280, ppg. 3 - 5.
i Objectives 1, 2, 3
H
. , - - , . - . - . - - - - - --
.
. - - - - - . , , . _ - - . ~ . - , - - - _ . , , -
. .
. INSTRUMENTS AND CONTROLS PAGE 31 ___________________________ ANSWERS -- PEACH BOTTOM 2R3 -86/03/10-HAJEK, ANSWER 3.08 (3.00) Upscale or > 100,000 cps INOP Downscale or < 3 cps Not fully inserted and < 100 cps Range 3bvpassesDownscaleandRetractPermit.fisO}% Ran3e 8 bypasses Upscale and Inop ct ,JL % REFERENCE (l.0) N PBAPS LESSON PLAN LOT-0240, p . Objectives 4 and ANSWER 3.09 (2.50) m pids h Reactor Water Level M - 13 a (+ M Hi Rad riain Steam Line 3:<NFP B Hi Steam Line Flou 140 percent Hi Steam Tunnel Temperature 200 degrees F Low Reactor Pressure 850 psis (.L Au'D iiEFERENC E PBAPS LESSON PLAN LOT-0180. pg. 7 and T 4 Objective ge;1g in Le A) 12.0; 'ni dek /3'j95 ANSWER 3.10 (2.50) Closure of the steam admissionvalve[i40-l'31]. It will begin injection again when level falls to-48'. It will auto return from test to operating mod N It must be rese $ y h[edvM oversp,ud zA 'ne /' fa f Reset the initiation the initiation signal logic resetcircuitry by depressing S{OE-pushbutto b,'f * REFERENCE PBAPS LESSON PLAN LOT-0380, ppg. 5, B, 10, and 1 hb Objectives 2 and !
*
o l
. PROCEDURES - NORMAL, ABNORNAL, EMERGENCY AND PAGE 32 RADIOLOGICAL CONTROL
____________________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HAJEK, B. ANSWER 4.01 (2.00) This assures a source of water when RPV pressure is below the isolation setpoints of HPCI and RCI This prohibits dryuell spray when the tGrus water level is high enough to cover the drywell to torus vacuen breaker REFERENCE 'l PBAPS LESSON PLAN LOT-1560, Trip Procedure Cautions /Deses i 1 and 4 Objective .pa ANSWER 4.02 (2.00) RPV - level below -48' or unknown
- Drywell pressure is above 2 psig - Group 1 isolation - Scram condition with power > 3% or unknown Cont - Torus temperature > 95 F - Torus level outside 14.6' - 14.9' - Drywell pressure > 2 psis - Drywell temperature > 145 F (0.25 each)
REFERENCE PBAPS LESSON PLAN LOT-1560, p. Objective ANSWER 4.03 (2.00) Maximize Drywell Cooling Terminate Drywell inerting Maximize Drywe111 Cooling by' putting in service all available drywell chillers and drywell cooler fan CO.53 Terminate inerting by closing-the nitrogen supply valve. E0.53
- ._-.
.
.
. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 33
-_-
RADIOLOGICAL CONTROL ____________________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HAJEK, B. REFERENCE OT-101, pps. 1 - 2, Bases, p . ANSWER 4.04 (2.50) All Offsite power is lost concurrent with failure of D/G's to star . HPCI/RCIC Use of NON-AD5 relief valves ( 0.LT % 3M W h / M d" REFERENCE PBAPS E-28, Loss of All Offsite Power on Both Units, .pa ANSWER 4.05 (2.50) With one RWCU pump operating E0.53, and flow going to the vessel E0.53, excessive flow rates Ein e:: cess of 250 gpm3 could cause pump cavitation and damsge. [0.53 When water is being dumped to the condenser, E0.53 MG-74 may be fully opened because flow is limited Eto 200 gpm3 bv the dump flow control valve. CO.53 REFERENCE S.3.1.A, p , and elsewher ANSWER 4.06 (1.50) To minimize the plant transient during the # subsequent scram. CO.753 Also inserts an' additional P*I' T signal to maintain recire pumps at min speed should the 30% limiter circuit fail.EO,253 To prevent recire pumps from tripping during auto 13KV transfer following:s scram and turbine tri (0.5) EContinuous recire flow will prevent temperature stratification after the scram.] REFERENCE l PBAPS SE-2 Cardox Injection lnto the Cable Spreading ) Room - BASES p. 1, _ _ - - - . _ _
. . . .
. PROCEDURES - NORMAL, ABNORMAL,~ENERGENCY AND PAGE 34
------------' - -- ~~~~ -
RA5i5t55iCAL CBNTR5t ____________________ ANSWERS -- PEACH BOTTON 2&3 -86/03/10-HAJEK, D. ANSWER 4.07 (3.00) an automatic isolation would occur if they remained in service, the plant may require steam seal transfer at a much higher pressure - probably full pressur that the bypass valves open appropriatel REFERENCE PBAPS LESSON PLAN LOT-1530, and GP-2, pg. 12, Step 20, pg. 14, Step 4a. and ppg. 14 16, and 17, Steps 7, 20 and 36, respectivel Objectives 1 2, and .pa ANSWER 4.08 (3.00) Reduce power EO.53 until the decrease in vacuum stops. [0.53 . With the reactor at power, an excessive off gas release could occur EO.53 because the holo up pipe is bypassed. CO.5]
' Above 5 percent, significant amounts of hydrogen and oxygen are present E0.5J uhich could 7 ;
result in fire or explosion. [0.53 , REFERENCE ' OT-106 and Base .pa l ANSWER 4.09 (1.50) All-rod motion shall be restricted to one notch in either l direction CO.753, and the continuous withdraw suitch may becused to start the rod motion, but released after the rod begins to move. [0.753 ,y, g g g y 3 g g y ,,l h d a es , S k ,. + d REFERENCE d h d seNck ~ i u da % P *'")?*!* ^ ON-106, p , Caution at start of procedur A g L* ***d-
; +P8 i l
l
!
__ . ._, _ _ . . . .. , _ , _ . . . - . . _
. * '- .
4 PROCEDURES - NORMAL, ABNDRMAL, ENERGENCY AND PAGE 35 RADIOLOGICAL CONTROL ____________________ ANSWERS -- PEACH BOTT0d 2&3 -86/03/10-HAJEK, 8. K.
3-ANSWER 4.10 (2.50) It is essential for operator control of the E, H, and L relief valves at the Emer3ency Shutdown Pane E0.53 Since the valves are not ADS valves, they cannot be operated nithout a continuous source of air. E0.53 The procedure is provided to assure that the bypass signal is sealed in E0.53 by placing the valve control switches to close E0.5J with the bypass switches in bypass. E0.53 or (i) Place both DIA N2 valve bypass switches in the BYPASS position EO.53,f#then place DIA N2 valves CAD-2(3)?69A&B3 in the CLOSE position, CO.53[1)then in the AUT0/0 PEN positior. CO.5 . Note that the order is important.- Asf do 141 firfY la ^"g rM MJ S REFERENCE PBAPS SE-1, Bases, p . ANSWER 4.11 (2.50) General operating condition of the plant Specific operations performed Difficulties encountered during the previous shift Scheduled plant operations Equipment outages and maintenance work-in progress Status of all safety-related equipment and
. conditions Jumpers added as noted on Jumper: Status Sheet 0 5 each for any five REFERENCE PBAPSiA-7, p i
,
!
l
!
i
.
l
- . .- . _
. . ~ , ..
t TEST CROSS REFERENCE PAGE 1 GUESTION VALUE REFERENCE ________ ______ __________
'
01.01 2.50 TRL0000584 01.02 1.00 TRL0000543
~ 01.03 3.00 TRL0000544 01.04 3.00 TRL0000545 01.05 3.00 TRL0000546 01.06 3.00 TRL0000572 01.07 2.50 TRL0000548
- 01.08 3.00 TRL0000549 01.09 1.00 TRL0000550 01.10 2.00 TRL0000551 01.11 1.00 TRL0000552 ______ 25.00 02.01 2.00 TRL0000553 02.02 2.00 TRL0000554 02.03 3.00 TRL0000555 02.04 2.50 TRL0000556 02.05 2.50 TRL0000547 02.06 2.00 TRLOOOO557 02.07 3.00 TRL0000558 02.08 3.00 TRLOOOO559 02.09 3.00 TRL0000560 02.10 2.00 TRL0000561 ______ 25.00 03.01 2.50 TRL0000562 03.02 2.00 TRL0000563 03.03 2.00 TRL0000564 03.04 3.00 TRL0000565 03.05 2.50 TRL0000566 03.06 3.00 TRL0000567 03.07 .2.00 TRL0000568 03.08 3.00 TRL0000569 03.09 2.50 TRLOOOO570 03.10 2.50 TRL0000571 ______
~25.00 04.01 2.00 TRL0000573 !
I ' 04.02 2.00 'TRLOOOO574 , 04.03 2.00- TRL0000575 '
- 04.04 2.50 ETRL0000576 )
04.05 '2.50 TRLOOOO577 , 04.06 1.50 TRL0000578 i l 04.07 3.00 TRL0000579 04.08 13.00 TRLOOOO580 04.09 1.50 TRL0000581 04.10 2.50 TRL0000582 __
-, ._ .._ _ _ . . . . _ . _ . . -
. .. * ,
t
, . , -
TEST CROSS REFERENCE - PAGE 2 OUESTION VALUE REFERENCE ________ ______ __________ 04.11 2.50 TRLOOOO583 ______ 25.00 ______ ______ 100.00 _
.
o r.-i ,- , _ w ,- -- y p
htrRchtnct) . U. S. NUCLEAR REGULATORY COMMISSION RENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: PEACH BOTTOM 2a3 _________________________ REACTOR TYPE: BWR-GE4 _________________________ DATE ADMINISTERED: 86/03/10 _________________________ EXAMINER: HOWE, _________________________ APPLICANT: __ [ k ______ INSTRUCTIONS TO APPLICANT: __________________________ Use separate paper for the answer Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passins grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examinatior. start % OF CATEGORY ~4 0F APPLICANT'S CATEGORi UALUE TOTAL SCORE VALUE CATEGORY ________ ______ ___________ ________ ___________________________________ _l'5 00_i____ _75 00 _1__ ___________ ________ THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS _I'5 00_1____ _'5 00I_1__ ___________ ________ PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION _['5 00_1____ _1'_5 00 1__ ___________ ________ PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL l 25.00 25.00 ADMINISTRATIVE PROCEDURES, ________ ______ ___________ _____--- CONDITIONS, AND LIMITATIONS i 100.00 100.00 TOTALS ________ ______ ___________ ________ l
FINAL GRADE % l All work done on this examination is my own. I have neither givan not received ai ~~~~~~~~ 5PPL5C5sT 5~555 ETURE l t i 1
. - - _ - _ _ - _ _ _
__ THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 THERN0DfNAMICS ______________ QUESTION 5.01 (2.50) What is meant by the term BETA with regard to reactor theory? (1.0) B. How does an INCREASE in BETA affect the reactor's response to the same positive reactivity addition ? (0.5) C. From BOL to EOL, does the core average beta INCREASE, DECREASE or REMAIN THE SAME? EXPLAIN your answer, , (1.0) GUESTION 5.02 (2.00) UO-2 is a pocr conductor of hea Is this a good or bad charac-teristic for controlling a POWER excursion of a nuclear reactor? EXPLAIN your choice.
QUESTION 5.03 (3.00) A fuel pin, over a period of time, has a uniform coating of corrosion products about 0.001 inches thick buildup on its surfac Assuming that power generation within the fuel pin REMAINS CONSTANT during the time of the buildup, would you expect the following temperatures to increase, decrease, or remain the same during the buildup? EXPLAIN EACH ANSWE Fuel temperatur (1.0) Cladding temperatur (1.0) Coolant temperature surrounding the lower portion of the fuel pin (prior to the onset of boiling). (1.0)
(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)
;
i l f l I i
. - - - . , . - - - - . - ,, . - _ . . . - - - - . , . THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3
____ ______________________________________ ______________ QUESTION 5.04 (3.00) For each of the pairs of conditions listed below, state WHICH condition would have the GREATER differential rod worth and briefly, EXPLAIN WH Reactor moderator temperature of 150 des F or 500 des (1.0) For an inserted rod next to a fully withdrawn control rod or next to a fully inserted control ro [ Assume average (1.0) core flux is constant 3 An edge rod during startup after a maintenance outage or an edge rod during startup 10 hours after a scram from extended power operatio (1.0) GUESTION 5.05 (2.00) List (5) five heat inputs and (3) heat outputs that would be used to calculate a heat balance at your plan QUESTION 5.06 (3.00) Assume the reactor is operating at 100% power and one recirculation pump trips. Indicate how each listed indicated parameter would first change (INCREASE OR DECREASE) and briefly explain WHY? Reactor Power (1.00) Reactor Water Level (1.00) Feedwater Flow (1.00) ! QUESTION 5.07 (2.00) During a loss of coolant accident or loss of feedwater accident there are ; four (4) basic conditions or actions that must be satisfied or accomplished to MITIGATE the possibility of degraded CORE condition What are these conditions or actions?
(NOTE: Your answer should be limited to BASIC CONDITIONS or ACTIONS necessary to mitigate the possibility of degraded CORE conditions.) (2.00)
l l
(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)
l __ THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4
- - --------------------------------------
--------------
QUESTION 5.08 (2.00) How does " Critical Power' vary (INCREASE OR DECREASE) with; Inlet Subcooling Increase (0.40) b. Local Power Increase (0.40) c. Axial Power Peak (top) (0.40) d. Mass Flow Rate Increase (0.40) e. Pressure Increase (0.40) 00ESTION 5.09 (1.50) Concerning the APRh flux scram trip settting (Run Mode): CALCULATE the scram trip setpoint if the reactor is operating at 3000 MW thermal with most limiting LGHR node operating at 10 KW/ft. Assume an LGHR limit of 13.4 KW/ft, recirc flow =100%
(SHOW ALL WORK) (1.50)
.
QUESTION 5.10 (1.00) Explain how the temperature of the Circulating Water System affects condenser vaevu (1.0) GUESTION 5.11 (3.00) For each of the events listed below, state which REACTIVITY COEFFICIENT responds first, WHY, and if it adds positive or negative reactivit ! a. One Safety Relief Valve opening at 100% powe (1.0) b. Control rod drop at 100% powe (1.0) c. Isolation of a feedwater heater string at powe (1.0)
(muxxx END OF CATEGORY 05 *****)
; PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 5
_ ---------------------------------------- --
QUESTION 6.01 (2.50) , Assume the Feedwater Level Control System is being operated in 3-element control using reactor level detector channel 'A'. Reactor power is at 85%, steady stat For each of the instrument or control signal failures listed below, STATE HOW REACTOR LEVEL WILL INITIALLY RESPOND (increase, decrease, or remains constant) and BRIEFLY EXPLAIN W4Y in terms of what is happening in the Level Control System immediately following the failur (FOR EXAMPLE, your answers should include the following detail,
'Causes reactor level to decrease due to the Level Control System having a steam flow / feed flow error signal, steam flow < feed flow, resulting in a reduction in the speed of the feed pump turbines')
NOTE: A block diagram of the Feedwater Level Control System is attached for your referenc 'B' FEEDWATER PUMP line FLOW signal FAILS HIG (1.25) LOSS OF CONTROL SIGNAL to 'B' REACTOR FEED PUMP speed controlle (1.25) GUESTION 6.02 (3.00) For each of the HPCI (High Pressure Coolant Injection) System component failures listed below, STATE WHETHER OR NOT HPCI WILL AUTO INJECT into the reactor vessel, IF IT WILL NOT INJECT WHY, AND IF IT WILL INJECT, provide ONE POTENTIAL ADVERSE EFFECT OR CONSEGUENCE of system operation with the failed componen Assume NO OPERATOR ACTION, and the component is in the failed condition at the time HPCI receives the auto initiating signa The GLAND SEAL EXHAUSTER VACUUM PUMP fails to operat (1.0) The MINIMUh FLOW VALVE fails to auto open (stays shut) when system conditions require it to be ope (1.0) The HPCI pump DISCHARGE FLOW ELEMENT output signal to the HPCI flow controller is failed at its maximum outpu (1.0)
(m**** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
-_-_ -_ -. _-_
1 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 6
- _ _ _ = = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
QUESTION 6.03 (2.00) With the plant operating at 100% power, Recire M/A stations in MANUAL, an electrical fault causes the load control unit input to the EHC system to decrease to 90%. What will be the response of the following to this occurence, and why will that response occur? Continue your discussion to aproximately ONE MINUTE AFTER THE FAULT. Assume NO OPERATOR ACTIO (Note: An EHC block diagram is attached for your reference.) Turbine Control Valve Position (1.0) Turbine Bypass Valve Position (1.0) QUESTION 6.04 (2.50) For EACH of the following conditions, state whether a scram, half-scram, rod block, or no action is generated. For conditions that produce more than one action, state the more limiting action (i.e. half-scram is more limiting than a rod block). MODE SWITCH IS IN RU RPS bus B shif t ed from normal to alternate power supply Turbine trip at 201 power APRM Flow Unit B fails downscale Scram discharge volume level is at 35 sallons Load reject at 50% power (0.50 each) (2.50) GUESTION 6.05 (2.50) Regarding the Standby Gas Treatment System: What are Three (3) of the f our conditions which will auto initiate the system? Setpoints are require (1.50) B. Consider Unit 2 & 3 seperately. Indicate the primary and back-up ' FAN' (A,B, or C) and the primary and back-up
' FILTER-TRAIN' (A or B) for an auto init2ation signa (1.00)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
.
, - - , , - . w c -
-- - , , ,e, -
, --w-s
.. PLANT SYSTEh5 DESIGN, CONTROL, AND INSTRUMENTATION PAGE 7
______________________________________________________ QUESTION 6.06 (3.00) List the automatic start signals for the emergency diesel generators. Give setpoints where applicabl (1.50) Briefly EXPLAIN the response of the ESW/ECW systems with respect to a diesel generator automatic start . (1.50) GUESTION 6.07 (3.00) Assuming valid initiation signals exist, what two (2) conditions will close the ADS valves once blowdown has commenced. ASSUME NO OPERATOR ACTION ON ADS AND ADS REhAINS FULLY OPERABL (1.00) During blowiown the operator depresses the ADS A(B) reset buttonsi describe the response of the ADS syste (1.00) ADS may be manually reset (depressing the ADS reset buttons) only when what conditions are met? (1.00) DUESTION 6.08 (2.00) State the normal operating value or range of values for each of the parameters belo (1.0) Control Rod Drive system flo . Drive water to reactor differential pressur . Cooling water to reactor differential pressur Explain how the on-line flow control valve responds during a reactor scram and wh (1.0) GUESTION 6.09 (2.00) Explain how and why each of the following would affect INDICATED reactor leve Assume in all cases a change occur Equalizing valve on the level transmitter leaks throug Drywell temperature INCREASES over an extended period of tim (***** CATEGORY 06 CONTINUED ON NEXT PAGE mauxx)
I
.
:
I
!
_ . _ ._. _- -. . . . . . . . . . - - - - _ _ . ,
- . _ - . . . __ _
. _ . . -. . . ._ - - . . - . -.. -.- ._ .
, PLANT SYSTEMS DESIGN,' CONTROL, AND INSTRUMENTATION PAGE 8~
------ -- - - - - - - - - - - - - - - - - - - - - - -_ _ -- ___- _ - - - - - - - - - -
. QUESTION 6.10 (2.50) State four (4) modes of operation for the Residual Heat Removal System and briefly explain the function of eac (2.50) . d t
.
I
.
.
.
(m**** END OF CATEGORY 06 *****)
'
i !
! . f f
, y .,, - - - - - - - - - , - ,y . .. , , -
-
- v,-rr,-,.,,,, m - ,,g., ,,- , , . .,e ., ,. . , ,- - - - - . - ,r y #m ,--,w --(
--. PROCEDURES - NORhAL, ABNORhAL, EhERGENCY AND PAGE 9
~ ~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~ R5656LUU5 CAL EUsTRUL
____________________ GUESTION 7.01 (2.00) State the entry conditions for RPV Control and Containment Control TRIP procedures . (2.00) I OUESTION 7.02 (2.25) A complete loss of Drywell Chilled Water system has occurre i a. What three heat loads are affected? (0.75) l b. Which system is the backup cooling system to the drywell? (0.50) j c. This system also fails to remove the heat from the heat loads.
I What are the effects? (0.50) d. What action (s) must be taken within 5 minutes if the (0.50) backup system fails as well? QUESTION 7.03 (2.50) Concerning Procedure E-28, Loss of All A. C. Power on Both Units (STATION BLACKDUT) a. What is(are) the entry condition (s)? (1.0) What are the methods of reactor vessel level control during a station blackout ? (Two (2) Required) (1.0)
- What is the INITIAL method of reactor vessel pressure control? (0.5)
i GUESTION 7.04 (3.00) Procedure SE-2 CARDOX Injection Into the Cable Spreading Room, requires performance of the three immediate action steps listed below. Briefly explain the bases for performing each actio a. Runback recire flow to minimum on both units (1.0) Transfer house loads on both unit (1.0) c. Manually scram on both units and execute procedure T-100 on both units concurrentl (1.0)
(mmmum CATEGORY 07 CDNTINUED ON NEXT PAGE asamm) ' ,
l l
:
l
l _ _ _ _ _ . _ _ _ _
, PROCEDURES - NORhAL, ABNORMAL, EhERGENCY AND PAGE 10 RADIOLOGICAL CONTROL
____________________ QUESTION 7.05 (2.50) Concerning GP-3 Normal Plant Shutdown; The procedure cautions you to limit plant cooldown to less than 100 des F per hour. BRIEFLY explain why? (1.0) i In section GP-3B.1 for Depressuri=ation to less than 600 psig, power less than 1% ( hot standby ), the procedure instructs you to reduce primary system pressure by opening the bypass valve opening jack. While performing this step, the procedure REGUIRES you to closely OBSERVE the Main Stack Radiation honitors as depressurl:ation beSi ns, especially when the mechanical vaccum pump is oper ating and to ADJUST the depressurization rate _as required so that the Main Stack Radiation honitor does not exceed 1000 CPS and the Vent Stack Radiation Monitors do not exceed 1000 CP (1) What is the purpose of this requirement? (1.00)
(2) What is the basis of the 1000 CPS limit? (0.50)
GUESTION 7.06 (2.00) While operating at 90% power, an LPRM alarms hig You suspect an unexplained increase in reactivity as the caus a. In addition to other LPRh alarms, what are TWO other symptoms you would look for to confirm your suspicion? (1.0) b. According to procedure, when must you manually shutdown the reactor in this situation? (1.0)
(xxxxx CATEGORY 07 CONTINUED ON NEXT PAGE xxxxx) . . .-. - . - - . . _ _ _ - .. _ . _ . - - . . . . - . .
__ _ _ _ _ _ _ _ __ _ ____
. - .
l l
l l PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11
- ------------------------ --- sE5iBL55iCAL C59Ts5L
____________________
,
GUESTION 7.07 (3.50) On receipt of a valid reactor building ventilation high radiation alarm (due to spent fuel dama3e) during refueling operations: 1. What 2 automatic actions occur? (1.0) If a refueling accident occurred, and it was necessary to assess the potential offsite exposure, where would you find the procedure to perform the necessary calculations? (0.5) Excluding SRM operability requirements of Tech. Spec. 3.10.B, what are four abnormal conditions that would be reason to terminate fuel handling operations? (2.0) GUESTION 7.08 (2.00) Per Operational Transient OT-114, Inadvertent Opening of a Relief Valve, what are the 'IMMEDIATE OPERATOR ACTIONS * on an indication of a stuck open relief valve,(SRV)? BRIEFLY explain the purpose of each ste (2.00) QUESTION 7.09 (2.00) There is an unexpecteo or unexplained decrease in condenser vacuum * , Other than air leakage into the condenser Provide two typical events that could cause the decreas (1.00) 2. Provide the two "Immediate Operator Actions * that are listed in Operational Transient OT-106, Condensor Low Vacuu (1.00)
(xxxum CATEGORY 07 CONTINUED ON NEXT PAGE musum)
_ _ _ - - - _ . ._ _ . . - . . - - . PROCEDURES - NORMAL, ABNORMAL,. EMERGENCY AND PAGE 12
~ ~~~~~~
~~~~RI655LU55C L CU TR5L'~~~~~~~~~~~~~ ____________________ QUESTION 7.10 (2.25) Concerning procedure T-102, Containment Control; Using the attached figures ( curves T/T-1 and T/L-1 ), Determine the minimum required torus level allowed for the following conditions:
* Reactor Pressure = 1100 psig ' * Torus Temperature = 130 deg. F (1.0) What could be the possible consequence and briefly explain how this consequence could develop when existing conditions are on the unsafe side of curve T/L-4 and drywell sprays are initiated ? ( curve attached ) (1.25) .
QUESTION 7.11 (1.00) With regards to the ALARA program at PBAPS: In addition to maintaining a philosophy of radiation exposure control, what are two (2) responsibilit2es of ALL PECO employees at PBAP (0.5) 6. What is the specific responsibility of the Operations Section ? (0.5)
(xxxxx END OF CATEGORY 07 xxxxx)
l
,, a f
r - w ,- > , - - - - ~, , ,- . . _ , , _ _ . , _ . _ _ ___ _ _ _ _ _ _ _ _ _ , _ _
,, ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 13 GUESTION 8.01 (1.50)
As the Shift Supervisor, you have the authority to release safety related equipment for maintenance and surveillance testing. In occordance with the Procedure for Control of Safety Related Equipment (A-41), WHAT are three (3) of the four (4) items you have the RESPONSIBILITY to consider BEFORE you release the equipment? (1.50) GUESTION 8.02 (2.00) Consider the following situations and identify any that are reportable, within one (1) hour,'to the NRC in accordance with A-31, Procedure for Notification of the NR Example: Reportable in 1 hour - w., NOT Reportable in 1 hour - y., Assume no additional conditions in making the determination for each situatio , APRM F fails downscale, power at 75%. (0.5) UNUSUAL EVENT DECLARE (0.5) Reactor SCRAM from low level, no fuel in the reactor vesse (0.5) FIRE in the Technical Support Center, heavy damage reporte (0.5) GUESTION 8.03 (3.00)
'
Unit 3 is at 95% power and all conditions are norma Unit 2 is at 75% power.and all conditions are normal with the following exception: Core spray pump A has been INOP for two days.' //' During a diesel survie11ance test the diesel generator fails to star In accordance with the Technical Specifications, WHAT ACTIONS MUST YOU TAKE IN THIS SITUATION? FULLY REFERENCE ALL APPLICABLE SECTION (3.0) QUESTION 8.04 (2.00) Who has the responsibility for assuring that a shift reporting for work is adequately staffe (0.50) What is an adequate staff?(Limit answer to Licensed personel only)
(1.50) -(xxxxx- CATEGORY OB CONTINUED ON NEXT PAGE xxxxx)
.
s ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE .14
----------------------------------------------------------
.-
QUESTION 8.05 f2.00) The reactor operator i.s performing a surveillance of the High Pressure Coolant Injection System and due to system modification a procedural step becomes impossible to perfor a. Under this condition CAN a temporary change be made ' to the procedure?
(0.50) What three (3) ' key points' must be followed when making a temporary change to a procedure? (1.50) ,
GUESTION B.0o (2'.00) During a surveillance calibration test of the. torus to reactor building Vacuum Breakers you are informed that one of the differential pressure switches controllins actuation of one vacuum breaker was found inoperabl Using the attached copy of Tech Specs, answer the followin NOTE: PLANT is operating at 85% powe a. Has Primary Containment integrity been lost initially, and wil_1 it be lost if maintenance is performed on the pressure switch? (1.0) Can the plant continue to operate. If yes, under what conditionsi If no. why not? Reference any portions of Tech Specs used to
~
develop your answe (1.0) QUESTION 8.07 (3.00) A Unit 2 plant startup is in progress. The mode switch is in startup/ hot standby. All IRh's'are on ranges 8 or SRh "A' is' bypassed due to erratic indicatio SRM's 'B'and "C" fail,downscal The instrument technician in charge says repairs will take 2 days.
- Using the. attached Tech Specs, DETERMINE:
,
x If the startup can continu x What actions are to be take Fully reference all applicable sections of the Tech Specs used and JUSTIFY your answe NOTE: SRM TRIP FUNCTION LOGIC DIAGRAM ATTACHED (3.0)
-(xxaux CATEGORY 08 CONTINUED ON NEXT PAGE ***mm)
x_
.___ ADMINISTRATIVE PROCEDURES, CONDITIONS,'AND LIMITATIONS PAGE 15
______ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - == QUESTION 8.08 (3.00) The reactor is operating at high powe A TURBINE TRIP occurs causing e scram on HIGH FLUX: e. HAS a safety limit violation occured? WHY OR WHY NOT? (1.5) WHAT action (s) are you as the Shift Supervisor required to take when a safety limit has been violate (1.5) GUESTION 8.09 (1.00) What are the two responsibilities of Shift Supervision with respect to A-12, Ignition Source Contr ol Procedure prior to use of an ignition source for work in the reactor building? (1.00) GUESTION B.10 (1.50) You have been requested to expedite a work package for work in the reactor building. What are three radiolo3ical conditions to consider l in determining the need for a RWP? Give numerical values where , applicabl (1.50) l l l GUESTION 8.11 (2.00) Consider the Emergency Plant You are on shift when a complete loss of offsite and onsite power occurs for two minutes. Using the attached Emergency Plan, Appendix EP-101, define the category and classify the . even (1.5) l B. Answer TRUE OR FALSE: As the Emergency Director, you have the authority to de-escalate the emergency action level without the concurrence of the NR (0.5)
(xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)
___-__- - -_
. .
..
.. .
,
.
.
O. " ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 16 -
-
-----------------------__
e*6 l QUESTION 8.12 (2.00) List the Tech Spec bases for the selection of the RPS instrumentation setpoint (2.0) l
.
l i
!
i
(m**** END OF CATEGORY 08 ***mm)
l (************* END OF EXAMINATION ***xummmmmmmmm*) - ! _ _ _ _ . _ _ _ _ _ _ . _ . _
__
. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 17 - - - _- _ . - - __---
THERMODYNAMICS ______________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, A.
ANSWER 5.01 (2.50) BETA, the delayed neutron fraction, is the fraction of neutrons in the core that were produced by the delayed neutron precursor (1.0) As BETA becomes larger, the period is longer for the same reactivity additio (0.5) Decrease (0.25) As Pu-239 production increases (0.25), and U-235 decreases (0.25) the core aver 83e will decrease due to Pu-239's Beta being so much smaller (0.25). (1.0)' REFERENCE PBAPS LOT 1420 p.5,9. Specific Learning Objectives 1, 8, 9, 12.
ANSWER 5.02 (2.00) The fact that U0-2 is a poor conductor of heat is a good characteristic E0.53 during the excursion since the high buildup of heat in the fuel E0.53 causes a larger insertion of negative reactivity CO.53 which tends to limit the magnitude of the excursion. CO.53 (2.0) REFERENCE PBAPS LOT 1480 p. 10,11. Specific Learning Objective 2.
ANSWER 5.03 (3.00) Fuel temperature would increase E0.253 to get the needed delta T to transfer the heat to the coolant. The corrosion layer will require some delta T across it to transfer heat E0.753 (1.00) b. Cladding temperature would also increase CO.253 because the pin temperature increased and the cladding is.now transferring heat to the corrosion film instead of the coolant.CO.753 (1.00) c. Coolant temperature remains the same CO.253 since it is a function of pressure, which is maintained constant by the EHC system. [0.753 (1.00)
. - _ - .
. . .______ ___-. . THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE IB ---- --- - .------------------------------- --------------
ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, REFERENCE PBAPS LOT-1320 Fuel Element Temperature Profile, p.4, 6, 1 Specific Learning Objectives 1, 4.
- ANSWER 5.04 (3.00) a. At 500 des [0.253 As moderator temp increases, neutron leakage out of fuel bundles is increased. Thus the control rod is exposed to higher neutron flux and rod worth increases. [0.753 (1.0) The withdrawn rod.CO.253 Neutron flux is higher in this area, thus rod worth is greater.CO.753 (1.0) The edge rod 10 hours af ter the scram.EO.253 Ten hours after a reactor scram the xenon is at a peak and at the greatest I concentration where the power had been the highest. Thus the flux during a startup under these conditions would be shifted to the edge of the core resulting in higher rod worths.CO.753 (1.0) REFERENCE PBAPS LOT-1490 Control Rod Worth, , 8. Specific Learning Objective 5, GP-2 Normal Plant Startup, p.11 ANSWER 5.05 (2.00> INPUTS OUTPUTS 1. FEEDWATER @ 9 STEAM (O AN 2. REACTOR CLEANUP WATER (IN)#3) REACTOR CLEANUP WATER (OUT)(o.2r) 3. CRD WATER to >I FIXED LOSSES [#, mJut ,, o.6w.d- less)(o,2.-j 4. R E C I R C U L A T I O N P U M P H E A T I N P U T IP 5 )
- 5,. CCCC THERMAL FCWER '.25/RCCPC"SE) aw REFERENCE PBAPS LESSON PLAN LOT-1300, Thermodynamics Section 19, pg 4- Special Learning Objective No. _ _ _ _ - ____ -
l
1
! THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 19 THERMODYNAMICS
______________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, ANSWER 5.06 (3.00) Decrease [0.53 due to increased void content in the core as flow decreases. [0.53 (,,,) (1.0) b. Increase [0.5] due to increased voiding in the core [0. E and zecire pv;p ns icnger tok.n o avuiiun un the ennvlu .. [0. 253 -4 (1.0) Decrease [0.53 due to steam flow decrease [0.25] and level increase [0.25] (1.0) REFERENCE PBAPS LOT-1640 Flow Transients, transparency ti, p. 3; Specific Learning Objective No. ANSWER 5.07 (2.00) 1) Reactor made suberitica (0.50) 2) Limit reactor pressure to prevent Reactor Coolant System boundary degradatio (0.50) 3) Maintain adequate coolant inventor (0.50) 4) Provide cooling flow adequate to remove decay and stored energ (0.50) REFERENCE PBAPS LESSON PLAN LOT-1690,Pg. 13, SPecial Learning Objective N . ANSWER 5.08 (2.00)
: Increase,g (0.40) I'rrr::: DEcAE4JE (0.40) Decrease (0.40) Increase (0.40)
e. Decrease (0.40) i REFERENCE , PBAPS LESSON PLAN LOT-1360,pgs. 7&8. Specif'ic Objective N ' ! l
. .
_
. THEORY OF NUCLEAR POWER > PLANT OPERATION, FLUIDS, AND PAGE 20 THERMODYNAMICS
______________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, A.
ANSWER 5.09 (1.50) S <= (0.66 W + 54 -0.66 delta W)(FRP/MFLPD) (0.75) W = % Recirculation Loop Flow delta W = 0 for two recire, pump ope' ration FRP = Fraction Rated Power NFLPD = Maximum Fraction Limiting Power Density S <= (0.66 x 100 + 54)(3000/3293)/(10/13.4) (0.50) s <= 120 (0.25) REFERENCE PBAPS Technical S P ecifications 2.1. PBAPS LOT-1390 pgs. 2,3,848 Specific Learning Objective No. 2.
ANSWER 5.10 (1.00) The condenser acts as a saturation system.Therefore,the lower the temp-erature,the lower the absolute pressure will be or the better the vac-vo (1.00) REFERENCE PBAPS LOT-1190 pg. 16-19; Specific Learing Objective No. LOT-0500 pg. 11 Specific Learning Objective No. 1.
ANSWER 5.11 (3.00) Void Coefficient. ( 0.50 ) The decrease in pressure causes an increase in voids, ( 0.25 ) adding negative reactivity to the core. ( 0.25 )
(1.00) Fuel Temperature Coefficient. ( 0.50 ) The rapid addition of positive reactivity due to the rod removal causes an increase in power thus in-creasing fuel temp. ( 0.25 ) This causes negative reactivity to be added to the core. ( 0.25 ) (1.00)
c. Moderator Temperature Coefficient ( 0.50 ) The removal of feedwater heating causes a decrease in FW temp (0.25) adding pos. reactivity.(0.25) 1 (1.00) l REFERENCE PBAPS Reactor Theory Handout, Section 26 LDT-1440 pg. 2-5; Specific Learning Objective No. l l
- _ . .. -
l l l l l l PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 21
-----
=-= --
ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, A.
ANSWER 6.01 (2.50) Causes reactor level to DECREASE E0.253 due to the Level Control System having a STEAh FLOW / FEED FLOW ERROR, STEAM FLOW < FEED FLOW E0.53 resulting in an DECREASE IN THE SPEED OF THE REACTOR FEED PUMP TURBINES E0.5 (1.25) Reactor level CO.253 because the TURBINE SPEED shouldREMAIgtggNSTANT CONTROLLER WILL LOCK [+rW ... :::ts; f t:d :=p perd " t h e-SFEED LEVEL DEtiAWDED AT inE IW37sNT FRIGR TG T;;E CICt'^L LCSC E0 #3 (1.25 REFERENCE PBAPS LOT-550 Feedwater Control System, p. 12, 19. Specific Learning Object 2ve B.
ANSWER 6.02 (3.00) Will inject CO.25 Turbine seal leakage resulting in Potential air-borne act2vity in the HPCI room E0.75 (1.0) Will inject CO.25 Pump overheating and seal damage may result during low or no flow conditions E0.75 (1.0) Will not inject CO.253. Maximum signal from the flow element will cause the controller to keep turbine speed at minimum CO.75 (1.0) REFERENCE PBAPS LOT 340 p. 5, P&ID h-365, M366. Specific Learning Objective: Purpose ANSWER 6.03 ( ) gp pp A The TCVs will closeA10% CO.53 due to the load selector signal decreasing by 10% and being less than the pressure signal (0.5 (1.0) To pas * to'b Sf**m, Sleu ans The BPVs will operabyr10% E0.53 due to the throttle pressure increase that occurs when the TCVs shut CO.5 (1.0) REFERENCE j PBAPS LOT 0590, EHC Logic p. 11-15+ Specific Learning Objective * ;
1 l
l l l 1 PLANT' SYSTEMS DESIGN, CONTROL,: AND INSTRUMENTATION PAGE 22
------------------------------------------------------
ANSWERS'-- PEACH BOTTOM 2&3 -86/03/10-HOWE, A.
, ANSWER 6.04 (2.50) half-scram no action half-scram ( AC.L1utf 2,00 6tecx w 4,fy s fewest ) rod block scram (5 9 0.5 ea) (2.5) REFERENCE PBAPS LOT 300 RPS LP p. 8,11,12. Specific Learning Objective PBAPS LOT 270 APRH LP p. 6. Specific Learning Objective PBAPS LOT 070 CRDH LP p. 18. Specific Learning Objective ANSWER 6.05 (2.50) A.1. reactor water level O' 2. D/W press 2 psis 3. Rx B1dg exhaust 16 mr/hr 4. refuel floor exhaust 16 mr/hr (any 3 at 0.50 ea.)
- Unit 2
- PRIMARY: fan A, trairw Ahp B/U: fen B, trainsAfA (0.50)
'
Unit 3: PRIMARY: fan C, train > B/A B/U: Fan B, tr air 6 B // (0.50) Note: On initiation both iso. dampers oPen so both trains in servic REFERENCE PBAPS LOT- 0210, REV 0, pg 3,5,7. Specific Learning Objective 3.
,
:
l
._ _
-
- _
- - _ _ ._ _ . _ - _
- - _ _ . _ . . . _ PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 23
______________________________________________________
>
ANSWERS -- PEACH BOTT0h 2&3 -86/03/10-HOWE, ANSWER 6.06 (3.00) . Triple low reactor water level -130' (-160 by T/S) 2. High D/W pressure 2 psig o,5 660 3. Loss of off-site power (under voltage) (-&T e a c h ) LLe&&) l On an auto sta p of the D/G,(at255 rpm)theESWdischarge , , 3 7,- valve opens.( Both ESW pumps and ECW pump start after 22 seconds.( 61 23 seconds later if the oischarge pressure is availible from either ESW pump the ECW pump stops.qggg At T= +80 if pressure is inadequate valve h0498' Icicr g e t cl closes and M0841 opens and one ECW booster pump starts.+-4+ 4 2-v + H CW m 4 4 g -p g H D.'3ek. b /*ve' sga REFERENCE rn o i V/ -7 E c .J hv h 4. /u*b A*' /"~' PBAPS LOT-0670, REV 0, pg 3,19. Specific Learning Objectives 2, PBAPS LOT-680, p.4, 5. Specific Learning Objective ANSWER 6.07 (3.00) . Reactor pressure < 50 psi (0.50) Shutdown of the RHR and CS pump (0.50) The valve will close and the timer will reset and if signals exist the timer will restart. At the end of the timer cycle (105 sec.), blowdown will recommence if the initiation signal still exist (1.00) Level above -130 inches (0.50) and makeup to vessel available (0.50).
[Nf. 5. 5,fo, c p ,,,,, i/z) (1.00) REFERENCE PBAPS LESSON PLAN LOT-0330.ps , Specific Lesson Objectives 1 & 4.
i ANSWER 6.08 (2.00)
#f6ospam, 2 ~250/265 psid, 3-15/;8"psid do "135 As accumulator pressure decreases, charging flow increases. Flow is sensed upstream of chs. tap so hi-flow is sensed sending a minimum ,
position signal to the FC ;
(a. 3 ans. 9 0.333 ea., b. Sensed flow change concept 0.5, FCV change 0.5)
(2.00)
xDoes not include seal water flow l l
__ _ _ _ - _ _ _ PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 24 . ------------------------------------= -------------- ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, REFERENCE PBAPS LESSON PLAN LOT-0070, pgs. 5,9,8 10; Specific Objective ANSWER 6.09 (2.00) Indicated level would INCREASE. Reference les - variable les dp would < go to zer Indicated level would INCREASE. Reference les density would decrease due to temperature increase so reference les pressure would decrease so reference leg - variable les dp would decreas (1.0 es. ans.; level direction 0.5, dp direction / explanation 0.5) REFERENCE PBAPS LESSON PLAN LOT-0050, pg 20, Specific Objective . ANSWER 6.10 (2.50) LPCI - Inject low pressure water into core post-LOC . Containment Spray - Limit temperature and pressure in the torus and drywell post-LOC . Torus Cooling - Remove heat from the suppression pool wate . Shutdown Cooling - Remove decay and residual heat from the RV to
>
achieve and maintain cold shutdow . Fuel Pool Cooling - to augment or operate in place of fuel pool cooling H . Head Spray - to assist in RPV head cooling and der.~essurizatio (4/6 0.625/ concept - specific names or wording above not req'd.) (2.50) REFERENCE , PBAPS LESSON PLAN LOT-0370,pgs. 2 & 3; Specific Objective 1.
l l . - . . . , . . , - - . . . _ . . _ , _ _ . - PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 25 RADIOLOGICAL CONTROL ____________________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, A.
ANSWER 7.01 (2.00) RPV - level below -48' or unknown
- Drywell pressure is above 2 psis - Group 1 isolation - Scram condition with power > 3% or unknown b. Cont - Torus temperature > 95 F - Torus level outside 14.6' - 14.9' - Drywell pressure > 2 psig - Drywell temperature > 145 F (0.25 each)
REFERENCE PBAPS LESSON PLAN LOT-1560, . Specific Learning Objective ?. ANSWER 7.02 (2.25) g ,, pg4,,s Recirc motor coolers, DW weep cooler, and the drywell fan coil units. (PAVeJEcc /SAJP4 co cas,g) (0.75) RBCCW (0.50) c.- Drywell pressure will increase,(approachingtheLOCAsetpoint.)
The Reactor recirc pump motors will begin to overhea (0.50) The reactor recare pump must be runback to minimum and be tripped within five minute (0.50) REFERENCE PBAPS LESSON PLAN LOT-0150, pgs. 3,4,5,6,& 97 Specific Learning Objectives 1, 4, PBAPS ON-113, Loss of RBCCW.
ANSWER 7.03 (2.50) e. All Offsite power is lost concurrent with. failure of D/G's to star (1.0) b. HPCI/RCIC (1.0) Use of NON-ADS relief valves (0.5) 0.Ay M g.J Q 4fy
;
l
l I
. . .__ _ _ __ _ _ _ _ _ _
3/p/64
'
PSAf5 _
. ANSHER 7.05 Part 3 (2): , 'The 1,000 cps limit en the inmin stack and Reactor Building vent stack to gevent a 5 percent MPC release is stated in GP-3. However, the reascm for that limit is not given in that g. W nre. At the time that limit was placed in GP-3, the Tech Spec's limit for instantaneous off-gas release was 1 MPC. In line with that, ON-103 chose 5 percent of MPC (1,000 cps) as the action level for an ALERr. Because these two procedures are so closely related, a candidate should at least get partial credit for referencing the emergency action level for ALERT in CN-10 REERENT: ON-103, Rev. 0 /Y2C /&:
If & ~ l4 , L & d. &; f< 4
.
culX A .de p .
!
l
:
l
,
. _ - . - . _ _ . _ - _ _ _ - _ _ __ .. - _ - _ - _ _ -. _ _ - _ _ _ _
__ __
( PROCEDURES --NORMAL, ABNORMAL, EMERGENCY AND PAGE 26 - -----== ---- - ~ ~R 555L555C L C5sTR5L--
____________________ ANSWERS -- PEACH BOTTON 2&3 -86/03/10-HOWE, REFERENCE i PBAPS E-28, Loss of All Offsite Power on Both Units' P+1 ANSWER 7.04 (3.00) a. To minimi=e the plant transient during the subsequent scram.CO.53
.Also inserts an additional signal to maintain recire pumps at min speed should the 30% limiter circuit fail.CO.53 (1.0)
i To prevent recire pumps from tripping during auto 13KV transfer > following a scram and turbine trip 0df 0,51(yontinuous recire flow will prevent temperature stratification after the scramTp0.33 (1.0) Scramming the units will minimize the plant transient as systems
become uncontrollable after cardox discharSe.[0.53 In addition
; the saftey analysis (for Mod 674 automatic cardox initiation in the cable spreading room) assumes that the unit is shutdown prior to cardox discharge.CO.53 (1.0)
REFERENCE PBAPS SE-2 Cardox Injection Into the Cable Spreading Room - BASES , ANSWER 7.05 (2 50) a.k.his rate has been chosen based past experience with operating power plants. The associated time periods for heatup and cooldown cycles provides for efficient but safe plant operation)E9764 Also, the calculated stresses were within the ASME Boiler and Pressure Vessel Codes. Mv'J'l (1.0) 'l I (1) This limitation is to allow cooldown of the plant in minimum , time and still minimize the release of gaseous fission products to the environ (1.0) j ,
(2) 1000 CPS on the main stack and one reactor building vent stack monitor results in a 5% MPC release rat (0.5)
0K DEt M ALLiLT LEVEL AS Mst- 0 A) -103 REFERENCE l
l PBAPSGP-INormalPlantCooldown, p. 4, i
- PBAPS T/S . l l
t
- l i
. l L PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 27
- - ---------------- ~~~~REU55LbdEUAL E5NTR5L '
____________________ ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, ANSWER 7.06 (2.00) p a. Neutron Monitoring System high flux alarm g,, ,44,, ren s a s Rod Block honitor rod block and alarm ,, fjm j. o7-/oy Increase in flux on the IRM/APRM recorders ( 2 Of 3 at 0.5 pts each) (1.0) b. If positive reactivity insertion is unexplaine (1.0) REFERENCE OT-104 POSITIVE REACTIVITY INSERTION-BASE ANSWER 7.07 (3.50) { ,, gg) . Reactor building isolation on hi-hi radiition in building ventilation (0.5) and 2nitiation of SBGT(0.5) (1.0) Emergency Plan (EP-316) ( o p 1L h 6 4 . / A in ....../ ode m ) (0.5) Indication of criticality Loss of communication between control room and refueling floor Two or more IRh's fail in one channel Accidental dropping or damaging of a fuel element (0.5 each)
(Will accept additional items listed in Proc. FH-6C pgs.8&9) (2.0)
REFERENCE Emergency Plan, ON-104 Vent Stack High Radiation-Bases, PBAPS LDT-0200, pgs. 6&73 Specific Learning Objective No. ANSWER 7.00 (2.00) Place both loops of torus cooling in servicer (0.50) to preserve torus heat capacity and maximize heat transfer to river (0.50) (1.00) 2. If torus temperature reaches 95~ F, enter Procedure T-102 (Containment control) and execute it concurrently with OT-114 (0.50) to remind operator of entry condition in T-102 (0.50). (1.00) REFERENCE Operational Transient OT-114, Inadvertent Opening of a Relief Valve-Base _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. . _ - --
' PROCEDURES - NORNAL, ABNORMAL, ENERGENCY AND PAGE '2 B
~ ~~~~R D56LU656AL C6UTRUL'~~~~~~~~~~~~~~~~~~~~~~~
____________________ ANSWERS -- PEACH BOTT0h 2&3 -86/03/10-HOWE, A.
! ANSWER 7.09 (2.00) 1..a) Recombiner compressor failur j)Cirtwa% $$scy n M %
"
b) Failure of an air ejecto c) Off gas system malfunctio e)Lac Lap~ M) h (tworeqd[.G0.5each) (1.00) a) Reduce reactor power until vacuum stops decreasin (0.50) b) If a scram condition occurs, enter Procedure T-100(scram) (0.50) REFERENCE PBAPS Operational Transient Procedure; OT-106, Condensor Low Vacuu ANSWER 7.10 (2.25)
, G 1100 psig, HCTC limit = 151 des F (curve T/T-1) CO.333
- delta T HC = 151-130 = 21 des F CO.333 4 From curve T/L-1 ein. level = 10.9 feet CO.333 In this condition there could be insufficient noncondensable gases in the torus and the initiation and continuation of torus spray could create ne3ative pressures greater than the capacity of the vaccum breakersCO.753 resulting in potential destructive containment negative pressures.CO.53 REFERENCE
,
PBAPS T-102, Bases P. 8, 9, 13, 1 ' PBAPS LOT-1560 Learning Objective * Purpose ANSWER 7.11 (1.00) * participate in ALARA reviews a participate in job briefings and reviews a request an ALARA review when it may reduce occupational exposure ( 2 required E O.25 each) b. To maintain communications between Operations Shift Supervision and Health Physics staff concerning operational transients in a timely manner to reduce potential or actual occupational e:< p o s u r e . (0.50) REFERENCE PBAPS LOT-1770 p. 16, 29. Specific Learning Objective 4 3, ! .
: . . _ - - __. - . - - -. _ _ ... ._ - ... _ . _ _ - . ,,,,_ - - _
. ADMINISTRATIVE PROCEDURES. CONDITIONS, AND LIMITATIONS PAGE 29 ANSWERS -- PEACH BOTT0h 2&3 -86/03/10-HOWE, ANSWER 8.01 (1.50) a. The potentially degraded degree of protection available to implement safety actions when one subsystem of a redundant safety system is to be release b. The length of time the equipment or system may be out of service, c. The Technical Specification requirement d. Conditions other than Technical SP ecification which are related to Nuclear Safet (3 required at 0.5 each) REFERENCE Procedure A-41, Procedure for Control of Safety Related Equipment, ANSWER 8.02 (2.00) WHAN t- a., t h Not reportable Reportable /1 hour-- b., .5 for each for a total of 2.00 REFERENCE A-31, Procedure for Notification of the NRC, , 6, 11, 15.
, Specific Learning Objective. LOT-1570 4 ANSWER 8.03 (3.00) Unit Two D/G LCO 3.5.F.1. Cannot verife all L.P. core and containment cooling subsystems operable, thus 2nitiate a shutdown and place the reactor in a cold shutdown condition within 24 hour (1.5) Unit Three: D/G LCO 3.5.F.1 May operate for seven days provided 4.5.F.1 is satisfied, and 3 ^.A.1 la aetisfied se .e,vired by 3.7.0.3. EF (1.5) REFERENCE PBAPS T/S 3.5.F.1., 3.9.A.1, 3.9. Lesson Plan LOT-18003 Specific Learning Objective No. , v-
l
!
l l ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 30
---------------------------
ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, A.
ANSWER B.04 (2.00)
(oss a. Shift Superintenden .25)-
b. 1) One SLO (shift supervisor) on site at all time (4,45-) 01 2) One SLO (shift supervisor or staff SLO) stationed in control room complex at all time (4,46) 01 3) One RO for each reactor shall be in the contro room at all time t_0_2c-; ) One RO in the control room (available to relieve one of the RO's mentioned in three abov (445)03 5) A SLO plus the above during refuel operations to directly supervise core alteration ( 4,99) O'O ( o*2 l~ M ;"lN= 0.t & W ) Administrative Procedure, A-7, Shift Operations, pg. 7, Peach Bottom Units 2 &3.
ANSWER 8.05 (2.00) Ye (0.50) . The intent of the original procedure is not altere (0.50) The change is documented on the procedure and initialed by a member of shift supervision and one member of PORC to signify approva (0.50) 3. The temporay change must be reviewed by PORC and approved by the Station Superintendent within fourteen days of implementatio (0.50) REFERENCE PBAPS Administration Procedure A-3, pgs. 1 & ANSWER B.06 (2.00) Providing the repair procedure for maintenance on the failed pressure switch does not violate primary containment inte3rity, containment has not been los (1.00) Per 3.7.A.3.b. Reactor operation is permissable only during the cucceeding seven days unless such vacuum-breaker is sooner made operable and the repairs do not violate primary containment (1.00)
. - . - _ . ._ _ - --. - . . - --
5'3/26 l PBAPS l
;
I Answer 8.07 ' The response to this situation involves on interpretation of Tech Specs and a choice of two correct actions. The Tech. Specs allow two interpretations for the response to this situation. Note 1 of
,
Table 3.2.C states that the SRM's must be operable or tripped in - the Stortup mode. Note 6 states that the SRM's are bypassed when + IRM's are on range 8 or above. Because the SRM trip logic is bypassed when the IRM's are on range 8 or obove, tripping the SRM chonnels would have no effect, o;.d therefore is not required; and should be considered a correct answer os shown on the answer key and as accepted by the Resident NRC Inspector. To trip the SRM chonnel is o conservative action and ensures compliance with the Technical Specifications even if the plant conditions change. A conservative response that also ensures compliance with the Tech-nical Specifications should also be considered o correct answer, and does not make the other response incorrect.
) Either of the two correct answers should be accepted for this , question, or the question should be voide References: Tech Spec Toble 3.2.C Note 1 versus the LCO interpretation , s au.ept 6# S M ,
.
M~ % af K &
& & a & W-
.
- . - , - . - - , -v-------- - . - - - , - - - , , , - . , , , - -+<,-w . ----r,.+-p w own e.w n- y ~- ,een% -. ~
. _ _ _ _ _ _ _ _ - - _ ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE. 31 --------------------------- _ - =-----------------------
ANSWERS - PEACH. BOTTOM 283 -86/03/10-HOWE, ' REFERENCE PBAPS Tech. Spec. 3.7. ANSWER B.07 (3.00) Yes the startup can continue (0.5) No action required (1.0) as long as IRM's are above range B since all SRM rod blocks are bypassed when the IRM's are on range 8 or above. (1.0) T/S 3.2.C table 3.2.C action does not apply.(0.5) (3.0) REFERENCE PBAPS LESSON PLAN LOT-0240, pg PBAPS T/S 3.2.C Table 3. ~ ANSWER 8.08 (3.00) a. YES, a safety limit violation has occurred.EO.53 A Safety Limit is assumed to have been exceeded if the scram is accomplished by a means other than the primary source signal.E1.03 * The unit shall be shutdownEO.53
* Immediately report the violation to* NRCCO.173, Superintendant Generation Nuclear (alternate: Fossil)EO.173 Committee [0.163 x Prepare and submit a safety limit violation r p tEO.53 REFERENCE PBAPS Technical Specifications, 1.1.C BASI PBAPS LOT-1820 p. 17, Specific Learning Objective # 4, ANSWER 8.09 (1.00)
1) Approval / Disapproval of proposed job per Appendix A of A-12 or Approval / Disapproval of performance of jo (0.50) 2) Determine type and number of fire watchers required for the job.(0.50) REFERENCE . PBAPS Procedure A-12 pg. _ _ _ _ _ _ ._ _ -- - _ _ __ - ____ _ ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 32
----------------------------------------------------------
ANSWERS -- PEACH BOTTOM 2&3 -86/03/10-HOWE, ANSWER 8.10 (1.50) 1) Entry into high radiation areas (>100 arem/hr) - 2) hw 1 . 1, :u:P that d~imr L : ' 1^^ . < - , 'cj M
3) Significant work where surface contamination is > 10,000 dpm/100 cm 4) Airborne contaminations requiring respiratory protectio ) Potential exists for exposure to high levels of radiation and contamination during work assignmen (3 req'd 0 0.5 each) (1.5) REFERENCE PBAPS LOT-1760 pg. 5; Specific Learning Objective N . ANSWER B.11 (2.00) Category: Loss of Power (0.75) Classification: ALERT (0.75) B. TRUE (0.5) REFERENCE PBAPS EP-101, PBAPS Appendix EP-101, PBAPS LOT-1520, Specific Learning Objectives 5, 6, ANSWER 8.12 (2.00) A/U*e h $*- . m to preserve the integrity of the fuel cladding W &7 m to preserve the integrity of the reactor coolant system /. D a to minimi:e the energy which must be absorbed following a LOCA o,y a to prevent anadvertant criticality 0 5 e e C E- I;7 2 00 total g . , . , ,_,
~ " ' " '
,,,, M ,l
REFERENCE PBAPS Tech Spec 3.1 Bases, % ,.ne-A * W W S t.4 % A "> ^ : # 'm & l: d , S W W ;& M y . . WA
-
YM ) L . m p~ Wg *S 7P%
% %_
&n
-,
aO
'
. _ __ _ __ . TEST CROSS REFERENCE PAGE 1 DUESTION VALUE REFERENCE
*
05.01 2.50 AXA0000065 05.02 2.00 AXA0000068 05.03 3.00 AXA0000132 05.04 3.00 .AXA0000134 05.05 2.00 AXA0000137 05.06 3.00 AXA0000140 05.07 2.00 AXA0000141 05.08 2.00 AXA0000142 05.09 1.50 AXA0000145 05.10 1.00 AXA0000157 05.11 3.00 AXA0000158 ______ 25.00 06.01 2.50 AXA0000069 06.02 3.00 AXA0000071 06.03 2.00 AXA0000072 06.04 2.50 AXA0000124 06.05 2.50 AXA0000125 06.06 3.00 AXA0000126 06.07 3.00 AXA0000138 06.08 2.00 AXA0000160 06.09 2.00 AXA0000161 06 10 2.50 AXA0000162 ______ 25.00 07.01 2.00 AXA0000127 07.02 2.25 AXA0000129 07.03 2.50 AXA0000133 07.04 3.00 AXA0000135 07.05 2.50 AXA0000136 07.06 2.00 AXA0000163 07.07 3.50 AXA0000166 07.08 2.00 AXA0000169
'07.09 2.00 AXA0000171 07.10 2.25 AXA0000212 07.11 1.00 AXA0000213
______ 25.00 08.01 1.50 AXA0000130 08.02 2.00 AXA0000131 08.03 3.00 AXA0000139 08.04 2.00 AXA0000143 08.05 2.00 AXA0000147 08.06 2.00 AXA0000148 08.07 3.00 AXA0000153 08.08 3.00 AXA0000155 08.09 1.00 AXA0000214 , I
;
l l
;
.~. . . . . - . . .. --. . - - . . . . . - . - . - - . -. _ - . -
,._
:
i
1 i ! t
!
- . _ TEST CROSS. REFERENCE PAGE 2 GUESTION VALUE REFERENCE i
- - ________ ______ __________.
A " 08.10 1.50 AXA0000215 08.11 2.00 AXA0000216 ! 08.12 2.00 AXA0000217 1 _____ i 25.00 ______ , . . ______ . I t 100.00
, -
4>
.
t .
, .
i
!
d .< J . i i J l
i l l I a
!
! !
I l e i
4 f
$
I -! l y ' i l
! ! - ,
}
4 I i. - - - .-...-.,_.... _ _ - . ..._, ,.-._.. - ,. ..--m.._-,_,_-,_.m..-~,.....__,r--..__ t---- -..-,---.. ,,,, , . ~ . . , _ , . _ , . , - - , - -
i . . , . . . . _ _ :-- --'~~ " """ '- ^
'
=
-
. -
~
. .
.
,
EQUATION SHEET , f = ma v = s/t Cycle efficiency = (Ne:wcet out)/(Energy in) i
= = ag s = V t + 1/2.at 2
I E=E KE = 1/2 mv a = (Vf - V,)/t A = IN A=Ae' g ) PE = ogh V =V + at w = e/t A = an2/t f = 0.693/t; NPSH = 9P , - 73 ,g ' t " EI 1/2 IIIb d 1/2'
, - ,
m o eAV
[(tif2) + (tb))
!
AE = 931 Am !
, I = I ,e' *
Q = mC;at Q = UAah I = I e~"* Pwr = W ah I=I 10-* f a TVL = 1.3/u-P = P,10 sur(t) - HVL = -C.693/u P = P,e*/I SUR = 26.06/T SCR = 5/(1 - K df I ' CR, = S/(1 - K ,ff,) j SUR = 25e/t= + (s - e)T CR)(1 - Kg f)) = CR 2 (1 - kgg) T=(z=/o)+[(s-e}/$o) M = 1/(1 - Kgf} = CR;/CR 7 = t/(a - s) - M = (1 - Kgfg)/(I - Kgf3 7 = (a - s)/(ao) l ' SDM = (1 - Kgf)/Kg,
,
a = (Kgf-1)/Kgf = AKgf /K df t' = 10-' sec:nds ,
!
t A = 0.1 secones~' l 8 * [(1"/(I K d f !] ^ 58eff /I ^ 1
'
Idl3=I#2 ,2 2 P = (t4V)/(3 x 1010) 1d gd 33 22 i t = .N 2 R/hr = (0.5 CE)/d (meters) NPSM = Static head - h y-P, 3 R/hr = 6 CE/d2 (feet) .. Water Parameters Misteilaneous Conversions 1 gai. = 8.345 lb . curie = 3.7 x ICIC::ps 1 gaj. = 2.78 liters 1 kg = 2.21 lam .
1 ft = 7.48 ga . I no = 2.5% x 104 E tw nr Density = S2.a lo /ft' i Density = 1 ge/c9 I mw = 2.41 x 106 Stu/hr Heat'of vapori:ation = 970 Btu /lbe lin = 2.54 cm Heat of fusien = 1** Et. / ism *F = 9/5=C + 32 t Atr. = 14. 7 ps1 = 29.i in. h * at = 5/9 (*F-32) _ _ _ _ _ _ . _ . . _ _ _ _ - ._- - - - - - - - - - - - - - - - - - ~
,
- ' ' ' ~~~~~~~~ ~ ~ ~ ' ~ ~ ' ~ ~ "~ l
~
, .., ,
. .w .
Table Saturated Steam: Temperature Table _ _ _ _ . . . . . . . . . . _ Sal Sa Sa Sa Sa Sa Temp iemp th per liquirl Ivap vapor Liquid Evap Vapor Liquid Evap Vapor Fahr e< Iabr SrlI I vg hI h fg hg sg sgg sg t E '.l_ . .. _. . *_Il . _ _. . 0.0000 2.1813 2.1813
'
0 016022 33041 33041 0 0119 07 .5 3 I O08859 2.1162 2 1802 3 '
<
0 016021 3061 9 3061 9 1.996 01 .4 0.0041 34 3 0 09600 3 .2 107 .0081 2 1651 2.1132 38 8 010395 0 0122 2.1541 2.1663 3 e s 011249 0 016019 26141 26342 6 018 01 .1 24458 2445 8 8 021 1011 0 101 .0162 2.1432 2.1594 4 s 1.12161 0 016019 0 016019 2212 4 / 221 .9 0 0202 2.1325 2.1521 4 ) 0 016019 2112 8 2112 8 12.041 106 .1 0.0242 2.1211 2.1459 4 e . 014192 108 .1111 2.1393 4 is 8 015314 0Dl6020 19651 19651 14 041 106 IR10 0 ' 1810 0 16 051 1066 4 108 .0321 2.1006 2.1321 4 .3 108 .0361 2.0901 2.1262 5 .2 108 .0400 2.0198 2.1191 5 $2 8 019165 0 20625 0 016026 1482 4 1482 4 22.058 106 .1 0.0439 2.0695 2.1134 5 ' 50 0 0 22183 0 016028 1383 6 1383 6 24 059 06 .0 0.0478 2.0593 2.1010 5 .2 26 060 06 .9 0.0516 2.0491 2.1008 58 4 BG I 025611 0 016031 12016 1201 6 28 060 10$ .7 0.05$5 2.0391 2.0946 6 .5
'
10886 0.0593 2.0291 2.0885 6 .058 05 .5 0.0632 2.0192 2 0824 6 St I O31626 0 016043 989 0 98 : 05 .4 0.0670 2.0094 2.0164 64 0 58 8 033889 0016046 9265 926 5 36.054 105 .2 0.0108 1.9996 2.0104 6 , lei O36292 0 016050 868 3 86 .0 109 .0745 1.9900 2.0645 78.8 'i 12 8 0 38844 0 016054 814 3 81 .9 109 .0163 1.9804 2.0581 1 .046 105 .8 0.0821 1.9108 2.0529 1 ,
'
18 I O44420 0 016061 111 4 111 4 44 043 10507 109 .0858 1.% 14 10412 1 le 0 0 41461 0016061 Gil R 613 9 46 040 104 .6 0.0895 1.9520 2.0415 it 0 80 0 0 50603 0 016012 633 3 633 3 48.031 104 .4 0.0932 1.9426 2.0959 0 It s 0 54093 0 016011 595 5 595 5 50 033 10413 109 .0969 1.9334 2 0303 1 .1 1098 2 0.1006 1.9242 2.0248 0 .026 104 .1043 1.9151 2.0193 0 i , 86 0 0 61518 III 0 65551 0 0160 %8 56 022 104 .9 0.1019 1.9060 2.0139 88.9 l lei O69813 0 016099 4681 4681 58 018 104 .8 0.1115 1.8910 2.0086 M.0 , If 8 014313 0 016105 441 3 441 3 60 014 104 .1152 1.8881 2.0033 9 Mt 019067 0 016111 416 3 41 .5 1102 5 0 1l88 1.8192 1.9980 9 > 96 I O84012 0 016111 392 8 392 9 64 006 1039 3 110 .8104 1.9928 ts O te s , b 90 0 GR9156 0 016111 310 9 310 9 66 003 1038 2 l104 2 0 1260 1.8611 1.9876
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ . _ _ _ _ _ _ _ _ _~
- - _ . _ _
.,
h l
'
P Ahn Pres Spaific Volume Entha!py [ntropy .
* tb pet Sa Temp Sa Sa Sa Sa $s Temp i
' ' lafie Sri ht lirlulil Ivap Vapor I.lquid Evap Vaper liquid Evap Vapet Fahr I p vig hl h is he sig sa t _ vi vs se 108 0 0 94924 0016130 350 4 350 4 67.999 103 .1295 1.8530 1.9825 10 .9 110 . :l331 1.8444 1.9775 10 % 5 0 016144 3131 313 1 71.992 103 .8 0.L364 1.8358 1.9725 1Ke les I i1347 0 016151 296 16 296 18 73.99 10336 110 .1402 1.8273 1.9675 1Es les I i2030 0 016158 780 28 78030 15 98 103 .5 0.1437 1.8188 1.9625 10 lig t 1.2750 0 016165 26537 265 39 77.98 103 .3 01472 1.8105 f.9577 11 .0 13$05 0 016173 251 37 251 30 19 98 103 .2 0 L507 1.8021 1.9528 11 .8 4299 0 016180 238 21 23822 81.97 1029I Ill t.0 0.1542 1.7938 ,.9480 11 .97 1027.9 ' 111 .1577 1.1856 .9433 li e e 16009 0 016146 714 70 f 214 21 85.97 102 ll 12.7 0.1611 1.7774 f.9386 11 ; its e . i6927 0 016204 203 25 * 703 26 87.97 1025 6 111 .1644 1.7693 1.9339 1M8 ' In s 1 7891 0 016213 192 94 192 95 89.96 1024 5 181 .1680 1.7613 1.9293 12 .8901 0 016221 18323 1324 91.96 102 .3 0.1715 1.7533 1.9247 12 I?$ 0 19959 0 016229 l14 08 : 14 09 93.96 102 .1 0.1749 1.7453 1.9202 1E0 12e e 21068 0 016738 15545 16547 95.% 102 .0 0 1783 1.7374 1.9157 1ES
! 13 .96 .101 .8 0.1812 1.1295 1.9112 138.8
- 13 .3445 0 016256 149 64
'
149 66 99 95 101 .6 0.1851 1.7217 1.9068 13 . 13 .41 101.95 101 .5 0.1884 1.7140 1.9024 1Rt 138 8 2 6047 0 016274 35 55 135 57 103.95 1016 4 11201 0.1918 1.7063 1.8980 1M8 13e e 21438 0 016784 :79 09 129 11 105.95 1015 2 112 .1951 1.6986 1.8937 13 I 28892 0 016293 122 98 123 00 107.95 101 ll2 .1989 1.6910 1.8895 1418 142 0 3 0411 0 016303 ll7 21 11722 109.95 101 .8 02018 1.6534 1.8852 14 til14 111 16 111.95 101 .6 0.2051 1.6759 1.8810 14 e 3 3653 0 016322 106 58 106 59 113 95 101 .5 0.2084 1.6684 .8769 14 e e 3 %181 0 016312 101 GR 101.10 115.95 100 .3 0.2117 1.6610 .8727 14 s 3 7184 0016343 9705 97.07 117.95 100 .1 0.2150 1.6536 .8686 128 1520 19065 0 016353 9266 9268 119.95 100 .9 0.2183 1.6463 . 8646 15 I 4 1025 0 016363 8850 88 52 121.95 100 .7 01216 1.6390 1.8606 15 I 4 3068 0 016374 84 56 84 57 123.95 100 .6 0.2248 1.6318 1.8566 156 9 ! 150 0 4 5197 0 016184 80 87 8083 125 96 100 .6245 1.8526 15 i
'
184 I 4 1414 0 016395 1727 7729 127.96 100 .2 0.2313 1.6174 1.8487 1E8 162 8 4 9722 0 016406 73 90 7392 129.96 100 .0 0.2345 1.6I03 1.8448 18 .96 99 .8 02377 1.6032 1.8409 10 les e 54623 0016428 6767 6768 133 97 99 .6 0.2409 1.5961 1.8311 10 Its 8 5 7273 0 016440 64 18 64 80 13597 99 .4 0.2441 1.5892 1.8333 18 , IIII 5 9926 0 016451 62 04 62 06 137.97 99 .2 0.2473 1.5822 1.8295 Ima
'
112 8 6 2136 0 018463 5943 59 45 139.98 99 .0 0.2505 1.5753 1.8258 17 .98 99 .8 0 2537 1.5684 1.8221 17 ; lit I 6 8690 0 016486 5459 $4 61 143 99 99 .5616 1.8184 1R0 171 8 1.1840 0 016498 5735 57 36 145 99 99 .4 0.2600 1.5548 1.8141 17 *
;
. - _ - _
g ., -]
;< *: * ,
Specific Volume [nthalpy Entropy kbsPress Sal Temp Temp lb per Sal Sat Sa Sa Sa Faht Sigi liqmtl Ivap Vapor Licvid Evap Vapor liquid Evan Vapor Fahr vg it hgi hg 5: Sig Sg i
! p vi vig 0 016510 50 21 50 22 148 00 990 2 1138 2 0.2631 1.5480 1.8111 10 .5110
* 0 016522 48 172 18 189 150 01 989 0 1139 0 0.2662 1.5413 18075 18 e 1 850 1.5346 I8040 1 .8 1139 8 0.2694 184 0 8203 02725 1.5219 1.8004 18 :.14 its 8 8 568 156 03 98 :14 .2156 1.5213 1.7%9 10 tes e 8 941 0016559 47 67I 42 638 0 016572 40 94 [ 40 957 158 04 98 .1 02787 1.5148 1.7934 19 '
02818
'
39 331 39 354 160 05 98 .9 1.5082 1900 19 . i 102 9 9 147 1.5017 .7865 l Ig4 0 0 016598 37 808 37 824 162 05 98 .7 0'.2848 .
: 0 168 '
36 348 36.364 164 06 98 .4 0.2879 1.4952 1.7831 19 les 8 0 805 0 016611 34 954 34 970 16608 97 .4888 1.7798 198 8 19e t I058 0 016624 33 622 33639 16809 97 .0 0.2940 1.4824 13764 29 ' 260 0 .
! 526 2 512 0 016664 31 135 31151 172.11 97 .5 0 3001 1.4697 17698 29 .0 3 568 0 016691 28 862 28 878 176.14 97 .3061 1.4571 1.7632 7:33 21 '
4 696 0016119 2G 182 26 199 180 17 91 .5 0.3121 1.4447 1.7568 212 0 ! 21s s ,5 901 0 016747 74 RT8 24894 184 20 96 .0 0.3181 1.4323 13505 21 .t "
!ft 0 7. lac 0 018775 23 131 23 148 188 23 96 .4 0.3f41 14201 13442' 220 e 2240 8556 0 016805 21529 21 545 192.27 96 .9 0.3300 1.4081 13380 22 sI M1015 0 016834 20 056 20 073 196.31 960 0 115 .3359 1.3%I 13320 2200 .
21.567 0 016864 18701 18 118 200 35 95 .8 0 3417 I.3842 13260 23 t 232 8 236 0 23 216 0 016895 17454 17 471 204.40 954 8 15 .3476 13725 13201 236 0 240 0 24 968 0 016926 18 304 16 321 20845 95 .3533 1.3609 17142 240.0 ' 2448 26 826 0 016958 15 243 15 260 212.50 949 5 116 .3591 1.3494 11085 244.0 i 248 0 28 196 0 016990 14 264 14 281 216.56 946 8 116 .3649 f.3379A 13028 240 t j ' 30 883 0 011012 13 358 13 375 22062 94 .7 0 3706 1.3266 16912 2528 252 0 258 I 31 091 0011655 17 570 12 538 224 69 94 .1 0 3163 1.3154 16911 254 0 l tse 0 35 427 0 017089 11745 11362 22816 938 6 116 .3819 1.30(3 16862 260 0 i 284 0 37.894 0 017123 !!.025 11 042 232.83 935 9 1168 1 0.3876 12933 16808 26 .1 1170 0 0.3932 1.2823 1 6755 istl 9 27 .3 0.3987 1.2715 16702 27 rit I 46 147 0 017228 9 167 9 180 24508 92 .5 04043 1.2607 16650 276 0
.l l 200 0 49 200 0 017264 8 627 8 644 249.17 92 .0 284 0 52 414 0.01130 8 1280 8.1453 253 3 921 7 1115 0 04154 12395 16548 284.0
, 288 0 55 795 0 01734 7 6634 76807 25 .2290 16498 288 e 292 8 59 350 0 01738 12301 72475 26 .4 0 4263 1.2186 16449 29 R759 6 8433 265 6 913 0 1178 6 04317 1.2082 1 6400 296 8
- - - - - - - - - - - - - - - - - - _ __ __ _ _ _ _ . ._ -_ __ _
. _ __ _ _. _ _ . _ _
j k
,
.
,
I Y !
= . . . - . - . . - . . . . .
' femp Lb pet Sa Sa Sa Sa Sa Sa Temp 4 Iali Sq in liquiti fvan vapor liquid [vap Yapor liquid Evap Vapot Fahr .
'
t p . vg v f hl hsi hg s, s,g sg .I l _ I 300 0 6700$ 0 01745 6 4483 6 4658 2697 910 0 117 .1979 1.6351 300 0
- 36 .0 l180 9 0 4426 1.1877 1 6303 304.0 i 300 0 15 433 001153 5 1655 5 1830 218 0 9040 118 .1776 16256 30 til t 19 953 0 01757 54566 5 4742 2821 90 l18 .1676 1.6?09 31 .
j $10 0 84 680 0 01161 51613 51849 28 .9 118 .1576 1.616: 31 . ) $2 $9 643 0 01166 48%I 4 9138 290 4 894 8 1185 2 0.4640 1.1477 1.6116 320.0 1 324 0 94826 0 01110 4 6418 4 6595 294 6 89 .2 04692 1.1378 16071 32 .2 04145 t,- j 320 0 100 245 0 01174 f 4 4208 1.1200 1.6025 370 0 - 332 0 105 907 0 01779 4 1788 41%6 30 .2 0.4798 1.1183 1.5981 33 .0 i 111 870 0 01783 3 % 41 3 9859 30 .1 1189 1 0.4850 1.1086 1.5936 336 0 340 0
-
117.992 0 01181 3 1699 3 7878 311 3 878 8 119 .4902 1.0990 1$892 340 0 ! 344 0 124430 0 01192 3 5834 3 6013 315 5 875 5 119 .0894 1.5849 344.0 ! 340 0 131.143 0 01797 34070 3 4258 319 7 87 .1 0.5006 1.0799 1.5806 340 0 ,, 1 352 0 130 130 001ODI 3 2423 3 2603 323 9 868 9 189 .5058 1.0705 1.5763 35 M3 3.1044 32 .6 0 5110 1.0611 1.5121 35 ' i , e i 30 .3 86 .4 0.5161 1.0517 1.5678 300.0
- 304 0 160 903 001816 2 8002 2 0184 336 5 85 .2 0.5212 1.0424 1.5637 36 .0 169113 0 01821 2 6691 2 6813 340 8 85 .9 0 5263 1.0332 1.5595 36 I $1 .7 0 5314 1.0240 .5554 312.0 1 370 0 190 517 (101R11 24219 24462 349 3 848 1 119 .5365 1.0148 .5513 31 $4 $129 0.01836 2 3110 2 3353 353 6 h44 5 119 .5416 1.0057 1.5473 300 0 3 .9 84 l987 0.5466 0.9966 1.5432 304.0 1 300 0 215 220 0 01847 2.1126 2 1311 36 R3 .3 0 5516 0.9876 1.5392 300.0 i 302 0 225 516 0 01853 2.0184 2.0369 36 .4 119 .5567 0.9786 1.5352 392.0 j 20 I9798 194?? 370 8 8291 120 .56l1 0.9696 1,5313 39 !
'
l, 40 Olb64 I8444 19630 37 .9 120 .5667 0.9607 1.5274 400.0 i 40 .4 82 .5 0.5717 0.9518 1.5234 40 ! 400 0 270 600 0 01875 l6877 11064 38 .9 0.5766 0.9429 I.5195 40 l ! 412 0 282 894 0 01881 16152 16340 38 .2 120 .5816 0.9341 1.5157 412.0 i 410 0 295.617 001R87 15461 15651 392 5 81 .8 - 0.5866 0 9253 1.5118 41 .
, -
420 0 3081 2 001094 14808 4997 39 .2 120 .5915 0.9165 1.5000 42 l 4240 322 391 001900 14184 . 4374 40 .2 120 .9077 1.5042 42 .
'
420 0 336.463 0 01906 1.3591 1.3782 4057 79 .5004 42 .0 351 00 0 01913 130266 1.32179 41 .9 120 .4966 43 R87 126806 414 6 189 1 120 .4928 436 0
] ! 44 .19761 1 21687 419 0 785 4 120 .6161 0 8729 1.4890 440 0 ! 4440 397 56 001933 1.14814 1.16806 423 5 18 .0 ! 440 0 414 09 0 01940 1.10712 112152 4280 176 7 120 .4815 440 0 -" <?S 431 14 001947 I ns7M iniist m 777 1 lina A O Une n om 88Me /.u
-. _ _ . _ .
. n p .
,
..
I ' Ahs l' test ~ Sperif er Volunie [nthalpy intro 0y lenip lb per Sal Sal Sa Sa Sa Sa Temp
,
l lahi Sq lit liquirl Ivan Vapor liquid tvap Vapor liquid Evap Vapor Fahr i p vg vig , vg ht h is h g sg s ,, 5, t 480 0 46607 0 01961 0 97463 0 99424 44 S32 120 .6405 0 8299 1.4704 40 I 485 56 001969 0 935R8 0 95557 44 .7 0.6454 0 8213 1.4667 46 OR98R$ 0 91862 4501 754 0 120 .6502 0 8127 1.4629 46 R4 0 86145 0R8.129 455 2 749 3 120 .6551 00042 .4592 41 is e $4511 0nl997 0 R/%R 0 R4%0 459 9 744 5 !204 3 06599 01956 .4555 4 7 / 0 81711 46 .4518' 40 .6696 01785 1.4481 48 It 8
'
610 10 0 07011 013G41 0 15658 413 8 1291 120 .6745 01700 1.4444 40 . 012820 418 5 724 6 ]20 .4401 40 s 556 61 0 07014 06Rn6% 010100 4R3 2 719 5 12021 06842 01528 1.4370 49 $9 P 48 .2 0.6090 01443 1.4333 50 $84 0 10510 0 07053 052938 06499, 4921 709 0 120 .6939 01357 1.4296 50 $80 0 731 40 0 02062 0 60530 0 62592 49 .1 0.6987 01271 1.4258 50 $12 0 15112 0 02012 058218 060289 50 .5 01036 01185 1.4221 51 , 51s e 184 76 0 07081 055991 0 58019 50 .7 119 .4183 51 .0 68 .4146 52 '
$24 0 841 04 0 02102 0 51814 053916 51 .3 119 .6926 1.4100 52 $70 0 810 31 0 02112 0 49843 051955 ' 521 8 67 .3 01231 0.6839 1.4070 $2 ,
932 0 900 34 002123 0 41947 0.50070 526 8 6696 119 ~01290 0 6152 1.4032 53 $16 0 931.17 0 02134 0 46123 01:1757 5311 66 .4 01329 0 6665 1.3993 $36 0 i $4 M2 29 0 02144 1f 44361 ~ 0 46513 536 8 65 .) 07378 0 6577 1.3954 54 ' 4 $4 .8 65 .1 0.7427 0.6489 1.3915 54 , 640 0 102049 0 02169 0 41048 043217 546 9 645 0 119 .6400 3.3876 540.0 ! 5S20 1062.59 0 02182 039419 0 41660 55 .5 119 .6311 1.3837 552.9 i 558 0 1097.55 0 07194 0 11966 0 40100 557 2 63 .7575 0 6222 1.3797 55 . , . , { $800 1133.38 0 02201 0 36501 0 38114 56 .7 01625 06132 1.3751 $800 j $04 9 1110 10 0 02221 0 35099 0 31320 56 .5 118 .3716 564 0
50 .5 118 .5950 .3675 540 0
51 .5 11821 0 7775 0.5859 .3634 57 .2 118 .5766 1.3592 570.0 ' 50 .1 58 .0 03876 0.5673 1.3550 50 , j $44 0 136?? 0 02295 0 28153 0 31048 59 .4 117 .3501 50 :
- , 50 .8 01978 0.5485 1.3464 580.0
e 59 .6 0 8030 0.5390 1.3420 $12.0 j " 598 8 149 ?s475 0 21110 61 .8 117 .5293 1.3315 598 0 ? !
. . - - _ _ _ _ - _ . ___ _- _ _ _ _ _ _ _ _
. __ -
,
. .
.
,1 Y
a' i Ahs Ples Specific Volume . Enthalpy [nitopy temp th pee Sa Sa Sa Sa Sa Sal Temp Faht Sq in lirluid Fvap Vapor ll uld Ivap Vapot liquid Evap Vapet Fahr
' P ' L . _ . .'.! $._ .. _ _.'_8 I h 's hs 5 Sit 58 t 0.5196 sees
'
'
543 2 0 02364 024384 026747 61 .7 0.8134 3.3330
$ce t Ca j 0 02382 0 23314 0 25757 62 .2 '16 .8187 0.5097 .3284 tot 0 589 7 000 8 1637 3 0 02402 0 27194 0 24796 628 8 533 6 116 .4997 ..3238 Se i 012 0 '686 1 0 02422 0 21442 0 23865 634 8 5241 115 .4896 1.3190 81 sig I 135 9 0 07444 0 70516 0 77960 640 8 51 .4 0.8348 0.4794 1.3141 41 $200 A 179 ! 0 22001 64 .2 0.3403 0.4689 13092 820 0 824 0 1839 0 0 02489 018737 0 21226 65 ? II4 .3041 82 , $20 0 -
1892 4 0 02514 0118R0 0 20394 65 .1 0.8514 0.4474 .2988 82 .4 114 .8571 0.4364 1.2934 83 .0 638 0 20078 0 07566 016776 0IR792 67 .1' O8628 0.4251 1.2879 63 .1 45 .7 0.0808 0.4134 1.2021 64 .0 ill8 3 0 02625 0 14644 0I1269 685 9 44 .0 0.8746 0.4015 1.2761 64 .9 43 .0 0.0006 03893 1.2699 64 .15816 700 0 4181 11181 0.8068 03767 .2634 $$ , e5 R 017.187 0 15115 70 .1 0 8931 03637 .2567 83 i 040 0 23651 002768 011663 0.14431 71 .1 110 .8995 03502 1.2498 00 .0 243 .9 37 .6 0.9064 03361 1.2425 06 $80 0 24981 002858 010229 0 13087 73 .1 109 .9137 03210 1.2347 00 'j 012 0 2566 6 0 02911 0 09514 012424 14 .9 0.9212 03054 1.2266 67 i ei s 002970 0 08799 011169 7492 32 .6 0.9287 0.2892 1.2179 87 .0 2108 6 003b37 0 00080 0till? 75 .1 196 .9365 0.2720 1.2006 se .1 0 03114 007349 0 10463 768 2 29 .4 0.9447 0.2537'. 1.1984 88 .8 000 0 28514 0 03204 0 06595 0 09799 778 8 26 .0 0.9535 0.2337 l.1872 88 i 00 '.5 0 03313 0 05191 0 09110 19 .1 103 .9634 0.2110 1.1744 80 se A 0 03455 0 04916 0 08371 804 4 21 .2 0.9749 0.1841 1.1591 99 fee.$ D004 3 0 03662 0 03857 0.07519 82 .7 99 .9901 0.1490 1.1390 10 .0 313 .0 144 1 97 .0006 0.1246 1.1252 10 s D17 .2 10 .2 1.0169 0.0876 1.1046 70 s s ?!9 .0 6 .4 1.0329 0.0527 1.0856 70 .47* 3708 2 0 05078 0 00000 0 05078 90 .0 90 .0612 0.0000 1.0612 70s.47* .
.
i
' ' Critical temperature i n - - _ _ _ _ _ _ _ _
,
= ."h
-
:- .
,
.
Table 2: Saturated Steam: Pressure Table Specific Volume Enthalpy Entropy Abs Pres Tem'p Sal Sa Sa Sa Sa ~ Sa . Abs Pres th/Sg i Iaha liquirl Ivan Vapor ti uid Evap Vapor liquid Evap Vapor Lb75q I . p i V V V i hgg hg sg s gg S g p I ig g I08885 32 018 0 016022 3302 4 3302 4 0 0003 107 .0000 2.1872 2 1872 s.eeses , 9 25 59 323 0 016032 1235 5 1235 5 27.382 1060l 108 .0425 70967 8.25 I SS 39 586 0 016071 64 .5 47.623 1048 6 096 3 0 0925 1.9446 P.0370 ISO 10 01 14 0 016136 331 59 333.60 6973 10361 1058 0.1326 1.8455 .9781 .9 13 l.6094 .8443 30 10 0 L93 21 0 016592 38404 38 420 161.26 98 .I4 .2836 1.5043 .7879 1 /26 799 18017 970 3 115 .4447 .7568 14.890 15 0 , 213 03 0 016726 26 274 26 290 181 21 %97 115 .3137 1.4415 .7552 1 N , 227 96 0 016834 20010 - 20 087 19627 960 1 115 .3358 13962 1.7320 29 8 30 0 250 34 0 011009 13 1766 13 '436 21 .1 0.3682 1.3313 1.6995 3 I 933 6 1869 8 0.3921 1.2844 1.6765 4 Se 3 201 02 0 017274 8 4967 85140 250 2 9219 117 .4112 1.2474 1.6586 5 le g 292.71 0 017383 1.1562 1.1736 2672 915 4 117 .4273 1.2167 1.6440 set 70 g 302.93 0 017482 6 1875 6 2050 27 .8 118 .1905 1.6316 2 .1 90 .1 0.4534 1.1675 1.6208 8 to t 320 20 0 017659 4 8179 4 8953 2907 894 6 1185 3 0.4643 1.1410 1.6113 9 .82 0.017240 4 4133 4 4310 29 .6 118 .4743 1.1284 1.6027 lese Ile e 334 19 0 01782 4 0306 4 0484 305 8 8811 118 .1115 1.5950 11 l 27 0 01789 3 1097 3.7275 31 .4 0 4919 1.0960 1.5819 120 0 13e 6 347.33 0 01796 J4364 3 4544 31 .8 119 .4998 1.0815 .5813 13e e 148 1 353 04 0 01803 3 2010 3 2190 325 0 868 0 115 .0681 ..5752 140.0 ' 150 0 35843 0 01809 2 9958 3 0139 330 6 863 4 119 .0554 L.5695 15 .1 0 5206 1.0435 ;.5641 160 0 lilI 368.42 001821 2 6556 26138 341 2 85 .0322 .5591 170 0 l3 G2 8507 1896 9 0.5328 1.0215 8' . 5543 10e e les e 37753 0 0l R.11 2 3847 2 4030 35 .6 0.5384 1.0113 15498 19e 0 200 1 381.80 0 01839 2 2689 2 2873 355 5 842 8 119 .5454 20 fle 0 385 91 001844 2.16373 2 18217 359 9 83 .5490 0.9923 1.5413 210 0 2200 389 88 0 01850 2 06719 P08629 364 2 835 4 1199 6 0 5540 0 9834 1.5314
'
22 l97991 99846 3683 83 .1 0.5588 09748 .5336 238 5 243 5 39739 0 01860 l89909 l91169 372.) 828 4 1200 6 05634 0.9665 .5299 24 .84317 37 .1 0 5679 0 9585 5264 250 0 200 0 404 44 0 01870 ;15548 17418 379 9 8216 120 .5230 26 .9 05764 0 9433 . 5197 270 e 200 4 411.01 0 01880 163169 165049 38 .3 0.5805 0 9361 1.5166 2s ' '
,
3= w 290 0 414 25 Unl8RS- 157591 1.59482 390 6 812 0 120 .e 200 0 41735 0 01889 .52384 1 54274 394 0 80 .9 0 5882 0 9223 1.5105 300 0 150 0 431.13 0 01912 30642 1.32554 409 8 194 2 1204 0 0 6059 0 8909 I4%8 350 0 des e 444 60 0 nl9.14 1.14167 1.16095 42 .4847 400 e _ _ _ _ - - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ - - _ _ _ - _ _ - _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ -__ ____-
__
*
.
~
"~
Enthalpy Entropy Specific Volume Sa Sa Abs Pres .. Sa Sa Sa Ahs Pirt Temp Sal Vapor liquid Evap Vapot tblSq I .' Iahi llitulil . Ivsp Vapor lic uid Evap
'P 1h/Sclf it 1, h gg h, s, s ,, s, p d l' l vi v ia 't 1204 8 06360 0.8378 f.4738 454 8 103119 43 e 0 456 20 0 01954 101224 120 .5 7551 See s 46701 0 01915 0 90181 120 See t 550 0 416 94 0 01994 0 87181 12037 0 6723 01738 0 16915 471 7 732 0 14381 650 s tes e 486 20 0 07013 0 14967 120 .9 120 9 Tes t 850 0 494 89 0 0/032 0 6R811 120 l.4304 0 65556 4916 110 2 700 0 503 08 lin7050 0 63505 12001 0 7022 07210 14232 15 R0 0 60949 50 esee 150 0 510 94 0 07069 689 6 1l99 4 03111 0 7051 0 54809 056896 50 eses ese1 51821 0 02081 1198 0 03197 0 6899 525 24 0 02105 0 51191 0 53302 5!84 619 5 1.4032 900 0 950 0 050091 526 7 6697 l196 4 0 7219 06753 ese 6 531 95 0 02173 0 41968 11943 03358 0 6612 1 3910 350 0 0 45064 0 47205 5341 660 0 e50 0 53e 39 0 07141 650 4 119 .3910 1000 0 0 42436 0/4596 542 6 1850 t fece 5 544 58 0 02159 64 !!9 ,
0 02171 0 40041 0 42224 5501 13794 ilee 8 1958 0 550 53 631 5 118 .6216
' 0 02195 0 31863 040058 55 e e lies 0 556 28 622 2 118 . 038073 5648 1.3683 12006 l 1950 0 ,
0 36245 57 %9 1200 0 561.19 0 07737 0 14013 118 .5850 1.3630 125 $12 38 0 02250 1180 2 03843 05733 1.3577 13ee t 0 30722 0 32991 585 6 594 6 13000 $17.42 0 02269 117 .3525 1358 8 ' , 0 29250 0 31537 59 ; 13500 582 32 002288 117 .5507 13474 140 .8 0 8026 0 5397 1 3423 14500 0 02321 0 26584 028911 605 3 5614 I450 0 59130 558 4 117 *05288 13373 1580.0 -' 5 % 20 0 02346 0 25312 0 21719 6111 1.3324 155 .4 0 8142 0 5182 0 02366 0 24235 0 26601 1.3274 1800.0 i 15500 600 59 54 flef 8 604 81 0 24551 630 4 53 '16 .4911 l 1850 0 609 05 0 02401 G 22143 '158 6 0 8309 04861 .3116 1Tse 0 0 21118 073601 63 .2 I fles e 613 13 0 07478 0 4765 .3128 1158 8 l 022113 64 .1 1155 6 08360 ' 1750 e 411.12 0 02450 0 20283 0 841? 0.4662 .3019 I800 0 0 21861 648 5 503 8 115 .02 0 02412 0 19390 0 4561 .3030 1950 0 1800 0 0 8555 0 21052 6545 494 6 ll49 0 0 8470 1850 I h24 83 0 02495 '14 .2981 190 .4 485 2 1000 0 h2056 00?$11 0 7161 666 3 415 8 14 / I2931 1954e 1958 0 132 22 0 02541 0 16999 019540 0 4256 12881 20000
:
67 .3 0 8625 I 2000e 135 80 0 02565 0 16266 0 18831 683 8 446 7 143 '21ee c :t ' o flee 0 642 16 002615 0 14885 011501 1.2676 2200 6 0 16212 695 5 4267 1122 2 08828 03848 22000 64945 0 07669 0 13603 0 3640 1 2569 230s.0
0 15133 10 /121 0 12406 0 3430 1 2460 240 Oll7R1 014016 719 0 38 .3 0 9139 0 3206 1.2345 2500 8 668.11 0 02859 010709 l)13068 7313 flee t 2500 0 108 .2225
'
0 02938 0 09172 012110 74 .2091 ties 0 619 53 0 03029 0 08165 011194 75 st e 105 .9468 02491 1.1958 200 fece 0 1039 8 0 9588 0 2215 1.1803 2980 0 690 22 0 03762 0 06158 0 09420 7851 2547 I 2900 0 102 .1619 3000 0 695 33 0 03428 ' 0 05073 0 08500 80 ; 3000 0 99 .9914 01460 11373 3Ise t 100 28 0 01681 0 03171 0 07452 82 ee e 3100 0 5 .6 1.0351 0 0482 1.0832 105 08 0 04412 0 01191 0 05663 875 5 370s.2* i 3200 0 00 906 0 1 0612 0 0000 1.0612 3700 2* 105 41 00'.018 0 00000 0 0507R 906 0 l I / . Q
. - _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ . - - _ _ _ _ _ _ _ _ _ _ _
s ~-
~~
Start Ua 8P**d
.,
gn
,
Date Error ** .
~
,
1 TurWne Trip i j
Turbine _
,,,,
4 A _
-
% Flow IV R.-.t- .
.
--
v
-
Lv
-
-
latercept Velve
-
-
Speed CV Reg
- ' *
+ Speed * ,,
IV R*e i' Erro' Load Reject f O-88**d l kWt LVo + '
*
Y-"A t Turb W . 4 m 1 Remote ine/Dee Signel
,
i Speed - % Flow \
}
, 2j
,
,Il
[MOT ,,
lg NC
- d/dt f -
,
I t .e t Mester Flow
,
Start Up M *"
'" L'*d A Controiner ' i '
M *"" d 0 ' Munheek, SYNC Speed Not Seleeted # ' T. R.d,e , Au - , ! Flow Centro.' a j Munbeek en Lees of Stemt Coeling h
#"
! Throtti V Pressure
} -
Turbane tripped
-
3, g O A * _ pst y,,,;,,
+ BIAS 9, Centrol I
v PRESS y,p,, I w INC h4 MOT HVG ~~ i t lAselmu m * L .d Preneure Set + CamWned d % Flow Limit
.
. F l**
DEC '
pil " D B - BIAS '
, '
N g , o U
'"" .+
--
L s HVG ensee < LVG Velve
.
3 % nemend 4 a TRANSPARENCY #6 Small Lew ves.wn
, ,_
Ci.es . .e= i LOT-0590 f Sles Jeek T
- -- - - -.__--_ _ - - - . _ - - _ _ _ _ . _ _ . _ _ _ _ - -
_ _
, .
y Sexm V *
.
t '
,,,. ,p..d .. . <e.e, + Control i *
t,,,i 9 __
.
Mein steem _ 1P R FP "A"
~
8 FE 4 p
"*
ll Rn l O Con lf I FT 4C NY M PT ~ L L
]
4 eynm vel,e l _. _,. .,,)
- - " .== .- -" *
l ll F, O I
-
t Con UU g i L _.- .g }
<_ ; .to C BAl A 9 Setpoint
,0w
"" " --..=.-. q
,, L-O*" t -+ r ---.+ r - .- - -.
-- - q l j( j( , Level / Flow i g
Total Error Feel IIS" Jl geeeen Feed i f3 r l I
\ Flow #
3 tiement 83"9 88 Hyd l Errot Con trol Element
. seek MSC Control i
1 '
- J L '
o esoo l Opens on any con ~~~~-----===*~~~~ = = ===*-a== = 2200 immy trip or serem with
- MOU ett feed pumps > rot
4L
.
sees d }-- ^ ,,,, Feedwater Control _ Function Simplified Block Diagram MIA "'" oen 4-= SC' < ont olk, 4- TRANSPARENCY 1
-
, a4- 1.07-0550 d
.
,, c4- - - "*""*'
,
SRM ROD WITHDRAWAL C BLCCK CIRCUITS
1
%. 4 CLOSED ON CLOSED ON 1 *'
POSITIOa# 3 IRM A(E)
.A(B). :: oR AsOvE -: :sYPAss OFF 1RM SWITCH (Nues 2)
.SRM A(B; #areN s ON 1 x ie cessRu Ni
-
I
,y OrEN ON sRM j SAME IRM '~'" " " ' ' ' ,
E(F) -- AS :: E(F)
-
A(B) BYPASS _ _ CLOSEO ON
--sRM eYPASs SRM LOW ca.OSEO pt wens ON '
FORIRM RANcE ._
< s ces switch -- sRM RETRAC WEN WHEN ON RANGE 3 PE RMISSIVE-- -ADETWCTOR ABW ~
Y NOT FULLY CLOSED
,, 9 > 100 CPS INSERTED
.
,g -
SRM
-/
C(D) 7-IRM SAME AS C(D) :: :: C(D) A(B) N
::
l IRM G(H) ;; :: G(H) :- -
-- ,a
--
r-l . l . 10 i NOTE 1 - SAM 8NOP emnesses open en any et ideo felleesses eeN'
- ,
ROO S (1) HIOH VOLTAGE SUPPLY L ESS THAN 300 VDC, U C8ECENTE
@ SAODULE UNPLUGGED'
i G) DRAWER SELECTOR SWITCH NOT ON OPERATE! TRANSPARENCY 5 LOT-0240 l l ,
!
__ - - - - - .
_ _ _ _
.
-
-
-
CURVE T/L-1
- - -
Je - - HEAT CAPACITY
--
,
- C et TE T M 4 :- l 'd LEVEL LIMIT CURVE -
..J -
' saYWE1.1. SPRAY INITIATION g . - -
PRESSURE.. LIMIT CutVE ,
-
; -15 SAFE -
see . [ 14 3 280
. .
\
13 % gg 280 e d 12
%N ]g~*$_ ~
UN54FE
'
f [)1 x
'
g " 10 , i.=n" 200tee "
"'
>- I 139 I ' UNSAFE RJI t4s / 6
'
g5Ei*d
; ; S 80 < ,/ , -
SAFE
-
,
g 0 5 to 15 20 25 30 35 40 l '
: AT HC I f) 1 * * ** * -
Tomas PRESESRE (PsIc,
-
AT HC IN OF ;
'- '
0F HEAT CAPACITY TEW LIMIT FR0W CURVE T/T MINUS(-) 0F TORUS TEM EQUALS (=) 0F A Tyg
's_ CURVE T/T-1
_ HEAT CAPACITY TEMPERATURE LIMIT CURVE 220 210 ! ! UNSAFE u.200 1 190
%'
180 I170 ' U ISO % -
^
SAFE % %
. "= 1 5 0 3: 40
"130 120 0 200 400 800 000 1000
-
-
REACTOR PRESSURE (PSIS) Attachment
- _ _ _ _ __. . - _._-.
- APPENDIX EP-101 Piga 1 of 12, R:v. 'l :
UNPLANNED SHUTDOWN UNUSUAL EVENT ,
*' ALERT UNPLANNED SHUTDOWN 5 SCRAM WITH TRIPLE E LEVEL 1) controlled shutdown due to failure 1) scram alarm and to meet L. ) double low level alarm (-4B") and 2) any scram other than planned 3) triple low level alarm (-130") and 4) increase in containment pressure to greater than 1 psig but less than 2 psig on PR-2/3508 SCRAM WITH SMALL LEAK , 1) scram alarm and 2) double low level alarm (-48") and 3) triple low level alarm (-130") and 4) containment high pressure alarm (2 psig) and 5) containment pressure 2 psig or greater on PR 2/3508 . . .
SITE EMERGENCY GENERAL EMERGENCY SCRAM WITH LOCA SCRAM WITH IDCA --& NO ECCS
. ;
1) scram alarm and 1) scram alarm and 2) double low level alarm (-48") and 2) double low level alarm (-48") and 3) triple low level alarm (-130") and 3) triple low level alarm (-130") and 4) containmant high pressure alarm 4) active fuel range level indication (2 psig) and shows less than -226" on LI-2/3-2-Sa) . con +=4n= ant pressure 10 psig or 3-91A,'B and l greater on PR 2/3508 or . 5) failure to reset triple low level l L5b) con +=4nmant dose rate greater than alarm after 3 minutes and ) 105 R/hr on RI-8/9103A/C and 6) contain= ant high pressure alarm i RI-8/9103B/D (2psig) and 7) containment pressure greater than 20 psig'on PR-2/3508 or l B) con +=4n= ant dose rate greater than 106 R/hr on RI-8/9103A/C and . RI-8/9103 E/D .
- - . ~ . >. APPENDIX EP-101 Paga 2 of 12, Rev. 14 -
PERSONNEL INJURY . UNUSUAL EVENT *' ALERT (
, !
i N/A INJURY WITH EXCESS RADIATION EXPOSURE OR . CONTAMINATION 1) Contaminated injury warranting off-e site medical treatment or 2) an acute whole body exposure greater than 3 R
. . - . .
e SITE EMERGENCY GENERAL EMERGENCY
.
e N/A N/A
.
e
\
. .
.,
. APPENDIX EP-101 Paga 3 of 12, Rav.14 _ _ - _
' PRIMARY CONTAINMENT . - - , . - - - . . ... ..
NON-ISOLABLE LEAKAGE : 'IDSS OF PRIMARY CONTAINMENT INTEGRITY 1) Primary containment leakrate 1) Reactor Building vent rad effluent is greater than 0.5 percent of high rad alarm and inability to volume per 24 hrs. at 49.1 psig or maintain pressure greater than 2) N2 makeup system is not capable of 0.25 psig on narrow range maintaining pressure (not due to PR-2/3508 orr lack of N2). 2) Torus Room flood alarm with level decrease in torus FAILURE TO ISOLATE PENETRATION WHEN ISOLATED BY A TRANSIENT 1) incorrect valve position during Group I, II, or III isolation alarms
.
_
. .
SITE EMERGENCY GENERAL EMERGENCY LOSS OF PRIMARY CONTAINMENT INTEGRITY WITH IDCA . 1) erratic containment pressure N/A
- fluctuations above alam setpoints of 1.5 psig, and 2) Group II and III isolation alarms, and 3) Conrain= ant dose rate greater than 105 R/hr on RI-B/9103A/C and RI-8/9103B/D and g 4) Reactor Building area high temper-g tor 3 PR 2 3- 8-abnormally high, and Reactor Bld vent rad effluent high alarm, or, 1) containment high pressure alar Main Stack Rad effluent on PR O-17-- (2.0 psig), and 051 increasing due to SGTS. opera- 2) scram, and -
tio ) containment dose rate greater than I 105 R/hr on RI-8/9103A/C and RI-8/ 9103B/D, and 4) Reactor BTd7 Area Rad Nonitors Alaming, and 5) Vent Stack Rad Effluent mnnitor high alarm
. .
, - - --
} APPENDIX EP-101 . Paga 4 of 12, Rev R ADIO ACTIVE RELE ASE - *'
UNUSUAL EVENT ALERT
[ , \
INSTANTAIEOUS RELEASE EXCEEDING TECH ACTUAL OR POTENTIAL RELEASE 0.01 REM SPECS WHOLE BODY OR 0.05 REM THYROID 1) Liquid effluent release exceeding Tech. Spec. 3.8. ) UncontroJlable release for more than
'20 minutes from the:
2) Gaseous effluent release exceeding al main stack greater than 1.0 x 10 Tech. Spec. 3.8.C.1 which may be cps on RR 0-17-051 or
-
detected by the following: If all releases are from one Reactorgldgventgreaterthan 6.0 x 10 cpm on RR-2/3979 or f release pain ) Continued particulate or iodine re- A spike on the main stack greater lease such that analysis of particu-than 1.8 x 104 cps on late filter or charcoal cartridge RR-0-17-051 or results in the following estimated A spike on the reactor bld re ease rates: vent greater than 3 x 105 cpm main stack greater than 9.7 x 10 t on RR-2/3979 or uCi/sec or If the release is from more than one release point Reactor Bldg vent greater than I A spike on the main stack greater, 1.1 x 10 uci/sec or-than 6 x 103 cps on RR-0-17-051 3) Containment dose rate greater than o_r_ 104 R/hr on RI-8/9103 A/C and l A spike on the . reactor bld RI-8/9103 B/ vent greater than 1 x 105 epm on RR-2/397 SITE EMERGENCY GENERAL EMERGM W ACTUAL OR POTENTIAL RELEASE 0.1 REM ACTUAL OR POTENTIAL RELEASE 1.0 REM WHOLE BODY OR 0.5 REM THYROID WHOLE BODY OR 5.0 REM THYROID 1) Uncontrollable release for more than 20 minutes from the: 1) Uncontrollable release for more than 20 minutes from the: main stack greater than 2.0 x 10 E g cps on RR-7127 or- main stack greater than 2 x 10 on RR-7127 or- Reactor Bldg. vent greater than
[ 6 x 106 cpm on RR-2/3979 -or Reactor. Bldg vent greater than 6 x 107 cpm on RR 2/3979 or
-~
2) Continued particulate or iodine re-lease such than analysis of particu- 2) Continued particulate or iodine re-late filter or charcoal cartridge lease such than analysis of particu-results in the following estimated late filter or charcoal cartridge release rates: results in the following estimated release rates: main stack greater than 9.7 x 103 main stack greater than 9.7 x 104 uCi/sec or-uC1/sec or
- Reactor Bldg vent greater *than k 1.1 x 103 uCi/see or- Reactor Bldg vent greater than 1.1 x 104 uCi/sec or
-
3) Containment dose rate greater than 105 R/hr on RI-8/9103A/C and ) gtainment dose rate greater than
" ~
#"
RI-8/9103B/D RI-8/9103B/D
-_ ,
. ' APPENDIX EP-101 l Piga 5 of 12, R:v. 14 ) - -
FIRE uNuSu a EvExT ;,
, , uERT
.
\
FIRE IN PROTECTED AREA LASTING 10 MI . FIRE WHICH COULD MAKE AN ECCS INOP OR MORE AFTER INITIAL ATTEMPTS 'IO EXTINGUISH IT 1) Fire alarm and verbal report from SSV 1) Alarm and verbal report from SSV
,
l
- .
I
. . . .
SITE EMERGENCY GENERAL EMERGENCY l FIRE WHICH MAKES AN ECCS INOP FIRE WHICH CAUSES DAMAGE TO PLANT SYSTEMS SUFFICIENT TO LEAD TO OTHER GENERAL 1) Fire alarm and verbal report EMERGENCIES from SSV 1) Fire alarm and verbal report from SSV, and IOCA symptoms, ECCS, or contairn=nt failure
I l l
.
e
. - - - - . - - .--
_ . . - -
.- -
- APrEdDIX EP-101 l
'
P ga 6 of 12, RIv.14
'
ENVIRONMENTAL vNuSuAL EvENr y xtERT I EARTFQUAKE , EARTHQUAKE 1) An actual earthquake detected by 1) An actual earthquake beyond the seismic inst.rumentation systems Operating Basis Earthquake (OBE) ABNORMAL POND LEVEL ABNORMAL POND LEVEL 1) Conowingo Pond level on LI-2/3278A, 1) Conowingo Pond level on LI-2/3278A,B, B,C: C: a) greater than 113 feet g a) greater than 115 feet or
,
b) less than 104 feet without prior b) less than 98.5 feet without prior notification by notification by ,
TORNADO TORNADO 1) A tornado is observed on site 1) A tornado strikes the Power Block with identifiable plant d = age
,
HURRICANE HURRICANE 1) Hurricane is expected to cross 1) Station is experiencing a hurricane the station with winds greater than 100 mph -
, . .
SITE EMERGENCY GENERAL EMERGENCY EARTHQUAKE
.
1) An earthquake greater than Design Earthquake as detected on sai<rnic instruments ABNORMAL POND LEVEL 1) Conowingo Pond level on LI-2/3278A,B,C exceeding the following limits: a) greater than 116 feet g b).less than 87 feet
.
e
\
. APPENDIX EP-101 Page 7 of 120 Rev.14 1.OSS O F P'O W E R .
UNUSUAL EVENT
, , ALERT . LOSS OF OFFSITE OR ONSITE; LOSS OF OFFSITE AND ONSITE AC POWER FOR POWER LESS THAN 15 MINUTES 1) turbine generator trip with Startup 1) turbine generator trip with Startup Auxiliary transformer SU2 and SU3 Auxiliary transformer SU2 and SU3 unavailable for service for more unavailable for service and than 60 seconds o_rr 2) failure of all diesel generators to 2) loss of voltage on the four 4160 energize their busses, volt emergency busses or 480 volt load centers supplied from the four IDSS OF ALL DC POWER FOR LESS THAN 15 MI volt emergency busses for more , than 60 second ) less than 105 volts on the 2/3A,B,C & b distribution panels as indicated on Panels 2/3AD03, 2/3CD03, 2/3BDO3, 2/3DD03 and 2) less than 21 volts on the 24 volt distribution panels as indicated on Panels 2/3AD28, 2/3CD28, 2/3BD28, 2/3DD28 and 3) loss of all alarms . ( .
SITE EMERGENCY GENERAL EMERGENCY LOSS OF OFFSITE AND ONSITE AC POWER FOR IONGER THAN 15 MINUTES . 1) turbine generator trip with SU2 and SU3 unavailable for service for longer than 15 minutes and 2) failure of all diesel generators to energize their busses for longer than 15 minutes LOSS OF ALL 125 VDC POWER FOR IDNGER THAN 15 MINUTES
.
1) less than 105 volts on the 2/3A,B, C&D distribution panels as indicated on Panels 2/3AD03, 2/3CD03,2/3BD03, . 2/3DD03 for longer than 15 minutes and - 2) less than 21 volts on the 24 volt I distribution panels as indicated on l Panels 2/3AD28, 2/3CD28, 2/3BD28 l 2/3DD28 for longer than 15 min. and 3) loss of all alarms for longer than 15 mi . -
- , -
, *
APPENDIX EP-lOl Page 8 of 12, RIv. 14
'
SECOND ARY CONT'AINMENT
UNUSUAL EVENT ' ALERT IDSS OF SECONDARY CONTAINMENT INTEGRITY 1) loss of secondary containment integrity for greater than 12 hours N/A
. ( . .
SITE EMERGENCY GENERAL EMERGENCY
.
-
!
'
N/A N/A l
;
i
) . .
e t l l
l l
, , .- . _ . - .
_ _
* APPCNDIX EP-101 Paga 9 of 12, Rsv. 14 -
INSTRUMENT F AILURE t UNUSUAL EVENT ,
* ' ALERT SIGNIFICANT LOSS OF ASSESSMENT OR COM-MUNICATION CAPABILITY IN THE MAIN CONTROL ROOM 1) complete loss of all Main Control Room communication equipment N/A .
e e e SITE EMERGENCY GENERAL EMERGENCY
.
N/A N/A i
.
O t
~ .
TAPPENDIX EP-101 Paga 10 of 12, Rav. la ,
'
FUEL D AM AGE - < UNUSUAL EVENT s, ALERT
,
t 4 POSSIBLE FUEL DAMAGE ; FUEL DAMAGE 1) Air ejector discharge rad monitor 1) Air ejector discharge rad monitor high alarm and an increase of 500mR/ indicating greater than 2.5 x 10 4 mR/ hr within 30 minutes or a level of hr on RR 2/3-17-152, or 2.5 x 103 mR/hr as in5cated on 2) High coolant activity 7f 300 uCi/gm RR-2/3-17-152, or dose equivalent I-131, and main steam + 2) high reactor coolant activity as line high-high radiation alarm with 4 . determined by sample analysis equal resultant scram alarm, or to or greater than 2 uCi/gm dose 3) spcnt fuel damage resulting~in a - equivalent I-131 refueling floor e 2a radiation monitor
, alarm or a high radiation alarm on refuel floor exhaust rad monitor . ( . .
SITE EMERGENCY GENERAL EMERGENCY 1 i FUEL DAMAGE FUEL DAMAGE
.
1) Following conditions occur: 1) When at least 2 of 4 containment rad a) failure of control rods to fully monitors indicate levels greater insert on a scram and than 106 R/hr on RI-8/9103A/C and b) higher than normal readings on RI-8/9103B/D and contain= ant pressure LPRMs adjacent to not-fully- exceeds 10 psig on PR 2/3508
-
inserted rods and c) at least 2 of the 4 con +=4n= ant' rad monitors indicate levels
'
greater than 10 5 R/hr on
*
RI-8/9103A/C and RI-8/9103B/ ) Major damage to spent fuel in fuel s pool or uncovering of spent fuel as confirmed by a fuel pool area radiation monitor alarm and: - a) refuel floor exhaust radiation ~ monitor high alarm, or
, b) refuel floor area radiation monitor alarm or 3) Observed major damage to spent fuel
-
.
. -
- _ _ _ .- , . - _ , -
. _ _ , , -. . _ - - . . - , ,
__ y
APPENDIX EP-101 Paga 11 of 12, Rev.14
' ~
HAZARDS
' ( UNUSUAL EVENT '
ALERT
\ *
MODERATE HAZARDS SEVERE HAZARDS 1) Aircraft crash on or near site 1) Aircraft crash on the facility or as determined by shift Supervision missile impacts into the Reactor or Bldg. Diesel Generator Bldg. or 2) Significant explosion on or near HPSW pump structure as determined site as determined by Shift by shift Supervision or Supervision o_r, r 2). Explosion damage to facility affecting 3) Toxic gas release on or near site plant safety as determined by Shift as determined by shift Supervision Supervision or 3) Chlorine gas detected in the
. Control Room .
SITE EMERGENCY GENERAL EMERGENCY _ l i l l l
. -- , , , - --y- -.,y-, - , -m,-g ,- - -,7- - , , - , , - - , ,e-m-,-,,,3 y,- , - e-- --,,-
e APPENDIX EP-101 Pag 3 12 of 12, Rsv. 14
- ,
CONTROL ROOM EVACU ATION
,
UNUSUAL EVENT ALERT
*
REh0TE CONTROL ESTABLISHED 1) Evacuation of Main Control Room anticipated or required and control established at remote shutdown panels N/A as determined by Shift Supervision
. . ( .
SITE EMERGENCY GENERAL EMERGENCY REMOTE CONTROL NOT ESTABLISHED 1) Evacuation of Main Control Room and control of shutdown systems not established at remote shutdown panels in 15 minutes as determined N/A by Shift Supervision l l l l
!
.
.1 I
l
_ _ . , __ . _ ,
.
PBAPS !
( l-TABLE OF CONTENTS
,
Pace N .0 DEFINITIONS 1 LIMITING SAFETY SAFETY LIMITS SYSTEM SETTINGS TUEL CLADDING INTEGRITY .2 REACTPt bOOLANTSYSTEMINTEGRITY .
'
SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENTS APPLICABILITY , 34 REACTOR PROTECTION SYSTEM .2 PROTECTIVE INSTRUMENTATION .3 REACTIVITY CONTROL Reactivity Limitations A 99 Control Rods B 101 Scram Insertion Times C 103 Reactivity Anomalies D 105 , STANDBY LIQUID CONTROL SYSTEM ' 115 Normal Operation A 115 Operation with Inoperable Components B 116 Sodium Pentaborate Solution C 117 CORE AND CONTAINMENT COOLING SYSTEMS Core Spray and LPCI Subsystems A 124 Containment Cooling Subsystem (HPSW) B 127 HPCI Subsystem C 128 RCIC Subsystem D 130 Automatic Pressure Relief Subsystem E 131 Minimum Low Pressure Cooling System F 132 Diesel Generator Availability Maintenance of Filled Discharge Pipe G 133 Engineered Safeguards Compartments B .133 Cooling and ventilations Average Planar LEGR I 133a Local LEGR J .133a Minimum Critical Power Ration (MCPR) I 133b I A,endment No. 104 /108 _, , 2/7/85
.
' ,,u-.--- - ~ - . -- , ,2-.,p- +--m--w.-9,w-, *,m-w ww ,yy y---ww- ypww~---w-y 9, .m-- - -T- -
g- y ow,-r%.-. ,, p- a i <--wwem.-v.-wa
.
-
, .
* ', PBAPS
- * . ..
.
TABLE OF CONTENTS"(Cont'd) Pace l
-
SURVEILLANCE i LIMITING CONDITIONS FOR OPERATION , , , , REQUIREP_ENT$ ' _ I 2 . .. , 3.12 RIVER LEVEL'.,. ,, - .. .e :. .4.12*' 237-
,
.te:. i High River Water Level A 237
! Low River Water Level., . . B- 237 Level Instrumentation ..u- C: 238
,
3.13 MISCELLANEOUS RADIDACTIVZ MATERIALS SOURCES 4.13 240a
. - - -
.
. ... ..
3.14 FIRE FROTICTION .' -_ c . . ;. I ' . ; * .' ' . ' . : . . i N '4.14 240c
' Water Fire Protection Systes . A 240c CO2 Fire Protection Systes . . : 3 240g .
C' Fire Detection C 2401 , Fire Barrier Penetrations D 240j Water Suppression Systems E 240k
, yattery Rm. Vent. Flow Detector F 2401 ,
*
3.15 SEISMIC MONITORING INSTRUMENTATION 4.15 240t
,' MAJOR DESIGN FEATURES 241 ( ADMINISTRATIVE CONTROLS 243 Responsibility 243 Organization 243 Facility Staff Qualifications 246 Training 246 Review and Audit 246 Reportable Occurrence Action 253 Safety Limit violation 253 Procedures 253 Reporting Requirements . 254
, 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 < 6.14 Integrity of Systems Outside Containment 263 6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 6.17 Offsite Dose Calculation Manual .- 265 6.18 Major Changes .to Radioactive Waste Treatamar Systems 265 i
- - .
l
* , \ /
111 Amendment t:o. ' 37..f7, 73, 75,1102, ~ i 102/104 (Updated March 18, 1985) ,
..,-._,....._...m -.---.- , , , _ - - . . - . , .a-.,.- c---_--.-,- -ea. , ..m,, _ , - ,
___ _____ , _ _ _ - - _ - - - _ _ - _ _
* . . . , ,e PBAr3 .
Unit 2 j
, LIST OF TIGURES Fioure' Tit 3e Pace
... -
.
3. Minimum Temperature ifor Pressure - 164 . Tests such as required, by Section XI , Minimum Temperature f'or Mechanical' ~ 3. a l Heatup or Cooldown following Nuciear Shutdown * Minimum Temperature for Core Operation
-
3. b . .
(Criticality)
3. Transition Temperature Shift v c Fluence .- 3. Site Boundary and Effluent Release ' 216e Points
. , . '
6.2-1 Hanagelnent Organization Chart 2 . 6.2-7 Organization for Conduct of Plant 745 ) Operations - *
.e ,
l
; * l l
.
l
.
.
l L l l iva Amendment No. 86 ,102 December 31, 1984
-_
_ -.
-.. -- - . _ . _ - _ _ _ . . .
, -
,
'
l
- -
. 1
*
. PBAPS UNIT 3 LIST OF FIGURES
'(
/.
-
rigure Title Page
-
l 1.1-1 APRM Flow Blas Scram Relationship To Normal 16 ) Operating Conditions 1 4. Instrument Test Interval Determination curves 55 4. Probability of System Unavailability vs. Test 98 ' Interval '
. . ,.
3. Required Volume and Concentration of .' 12 2 "' ' Standby Liquid Control System Solution 123
~
3. Required Temperature vs. Concentration for Standby Liquid Control System Solution , 3.5. MCPR Operating Limit vs. Tau, LTA 142 3.5. MCPR Operating Limit vs. Tau, BP/P8X8R Fuel 142a 3.5. DELETED
.-- _ _ _ .
3.5. DELETED 3.5. DELETED 3.5. DELETED 3.5. Kf Factor vs. Core Flow 142d 3.5. DELUED l 3.5. DELETED 3.5. MAPLHGR vs. Planar Average Exposure, Unit 3 142g P8X8R Fuel (P8DRB284H) 3.5. MAPLHGR vs. Planar Average Exposure, Unit 3 142h ( P8X8R and BP8X8R Fuel (P8DRB299 and BP8DRB299) 3.5. MAPLHGR vs. Planar Average Exposure, Unit 3 1421 BP8X8R Fuel (BP 8DRB299H) 3.5. MAPLHGR vs. Planar Average Exposure, Unit 3 142j - PBX 80 LTA (P8DQB326) 3. Minimum Temperature for Pressure Tests 164 ' such as required by Section XI 3. Minimum Temperature for Mechanical Heatup or 164a i Cooldown following Nuclear Shutdown - l ' 3. Minimum Temperature for Core Operation 164b ',
(Criticality)
3. Transition Temperature Shift vs. Fluence 164c) 3. Thermal Power Limits of Specifications 16 4d * 3.6.'F.3, 3.6.F.4, 3. 6.F. 5, 3. 6.F. 6 and 3. 6. . Site Boun63ry and Effluent Release Points 216e 6.2-1 Management Organization Chart 244 6.2-2 Organization for Conduct of Plant Operation 245
.
!
-
! , l
'
l -iv-Amendment flo. If, fJ. /E, fE, E2, 79, 97. JSA 197 114(8-23+85) ;
. . _ - . .. _ . - . _
. _ _ - . .
.-
y ,
' . . i ) -
l
, ,,
, PBAPS,. .
'
..
)
' TABLE OF CONTENTS (Con t ' d)
l
-
Pace
-
SURVIILLANCI i LIMITING CONDITIONS FDR OPERATION RIOUIREMENTS ; 3.12 RIVER LEVEL 4.12 237 High River Water Invel A 237 Low River Water Level B 237 Level Instrumentation C 238
, 3.13 MISCELLANIOUS RADIDACTIVE MATERIALS SOURCIS 4.13 240a ~
3.14 FIRE PROTECTION , 4.14 240c Water Fire Protection Syste:n A 240c CO2 Fire Protection System B 240g Fire Detection C 240i Fire Barrier Penetrations D 240j Water Suppression Systems I 240k Battery Rm. Vent. Flow Detector F 2401 -
} 3.15 SIISMIC MONITORING INSTRUMENTATION 4.15 24,0t t - MAJOR DESIGN FEATURES 241 ADMINISTRATIVE CONTROLS 243 Responsibility 243 Organi:ation 243 Facility Staff Qualifications .
246 Training 246 Review and Audit 246 Reportable occurrence Action Safety Limit Violation 253 Froced'ures 253 ' Reporting Requirements 254 - 6.10 Record Retention 260 6.11 Radiation Protection Program 261
.6.12 Fire Protection Inspections 261 6.13 High Radiation Ares 262 6.14 Integrity of Systems outside Containment 263 6.15 Iodine Monitoring 263 f.16 Environmental Qualification 264 6.17 .Offsite Dose Calculation Manual 265
'6.18 Major Changes to Radioactive Waste Treatment Syst2ms 265
.
.
Amendment N #, # , '7), M, iii 102/104 (Updated March 18, 1985)
- . _
. . . _
-- ., - . . . - _ - . - _ . . , , - - -
- . .-_ - -_
.
.
i
-
,
*
,
*
PBAPS UNIT 3
-
LIST OF FIGURES
/(
,
\
!
- Figure .
Title Pace
;
!
1.1-1 APRM Flow Blas Scram Relationship To Normal 16 I
'
operating conditions 4. Instrument Test Interval Determination Curves 55 , 4. Probability of System Unavailability vs. Test 98 [
;
Interval 3. Required Volume and Concentration of 122 j Standby Liquid Control System Solution . 3.1. 2 Required Temperature vs. Concentration for 123 ! Standby Liquid Control System Solution i 3.5. MCPR Operating Limit vs. Tau, LTA 142 j MCPR Operating Limit vs. Tau, BP/PBXBR Fuel 142a
'
3.5. .5. DELETED ,,
- . - - - - - - -
i 3.5. DELETED - 3.5. DELETED f 3.5. DELETED l 142d
'
3.5. Kf Factor vs. Core Flow 3.5. DELETED l 3.5. DELETED l 3.5. MAPLUGR vs. Planar Average Exposure, Unit 3 1429 ! P8X8R Fuel (P8DRB284H) r 3. 5.1. I MAPLHGR vs. Planar Average Exposure, Unit 3 142h [ P8X8R and BP8X8R Fuel (P8DRB299 and BP8DRB299) 3.5. MAPLHGR vs. Planar Average Exposure, Unit 3 142i BP8XBR Fuel (BPSDRB299H) : 3.5. MAPLHGR vs. Planar Average Exposure, Unit 3 142j PBX 80 LTA (P 8DQB326) i 3. Minimum Temperature for Pressure Tests 164 '
,
such as required by Section XI . 3. Minimum Temperature for Mechanical Heatup or 164a l Cooldown following Nuclear Shutdown ! 3. Minimum Temperature for Core Operation 164b (Criticality) ,
3. Transition Temperature Shift vs. Fluence 164c : 3. Thermal Power Limits of Specifications 164d ; 3. 6.~F . 3 , 3.6.F.4, 3. 6.F.5, 3. 6.F. 6 and 3. 6. l 3. Site Boundary and Effluent Release Points 216e 6.2-1 Management Organization Chart 244 6.2-2 Organization for Conduct of Plant Operation 245 l
!
!
. ,
;
!
t
,
i l -iv-l Amendment flo. If, /7, M, JE, 57, 77, , ( $7.195. 707 114(8-23-85) [ t
$
__ _ _ _ . . _ _ . _ _ _ . , _ , _ . _ . . - - . . . _ _ - _ . _ _ . - _ . . _ . _ . _ . . ..__ .._.- . _ _ _ _ . . . _ . . _ . _ . ~ . , . _ . _
.___ _ ___ __
.-
*
. .
.
- . .
.PBAPS
*
- .
.
..
*
I.TST OF TAET M
'
.
Table , h gage 3. Reactor Protection System (Scram)
'
Instrumentation Requirement '
.
4. anactor Protection System (Scram) 41 Instrument Functional Tests 4.1. 2 Beactor Protection System (Scram) 44
.
Instrument calibration'
-
3. 2. A Instrumentation That I.nitiates Primary
.
containment Isolation 3. Instrumentation That Initiates or controls 44
.the core and containment cooling syktens 3. 2. C Instrumentation Tha . Initiates Control Rod Blocks -
-
_ 3. Radiation tionitoring systems That Initiate 75 and/or Isolates systems
. 3.2. F Surveillance Instrumentation *I7 ' 3. 2. G *
Inst::umentation P.tmp Tr.ip That Initiates Reci.htion 79 4. 2. A Musimum for PCIS Test and calibration Frequency 80
- .
., . e
. .
.
-
.
.-
. .
~ >
Amendment No. Jai,#, 112/116 e
11/19/85
..
_
.
I
-
\
- _ .. - _ _ . . . . . - - - - _ . . . - . . . . - - . . . _ . - . _ _ - . - -
.
h PBAPS LIST OF TABLES
!
'
Table Title Pace 4. Minimum Test and Calibration Frequency 81 for CSC9 4. ' Minimum Test and Calibration Frecuency 83 for Control Rod Blocks Actuatien 4. Minimum Test and Calibration Frequency 84 for Radiation Monitoring Systems 4. Minimum Test and Calibration Frequency 85 fer Drywell Leak Detection - 4. Minimum Test and Calibration Frequency 86
.for Surveillance Instrumentation 4. ' Minimum Test and Calibration Frequency 88 for Recirculation Pump Trip 3.5. Operating Limit MCPR Values for 133d Various Core Exposures 3.5. Operating Limit MCPR Values for 133e various Core Exposures 4. In-Service Inspection Program for Peach 150 ,
Bottom Units 2 and 3 3. Primary Centain=ent Isolation Valves 179 3. Testable Penetrations With Double 184 0-Ring Seals 3. Testable Penetrations with Testable 184 Bellows 3. Primary Containment Testable Isolation 185 Valves 4. Radioactive Liquid Waste Sa=pling and 210 Analysis 4. Radioactive Gaseous Waste Sampling and 211 Analysis 3.11. Safety Related Shock Suppressors 234d 3.14. Fire Detectors 240m 3.15 Seismic Monitoring Instrumentation 240u 4.15 Seismic Monitoring Instrumentation -240v SurveiJ1ance Requirements I Amencment tio. 102/104 ~Vi-(Updated March 18, 1985)
.
_ _ _ _ _
,
. .
O
- PEAPS
,
-
LIST OF TABLES , _' Table Title . Pace
. ,. . . '1'
Maximum Values for Minimum Detectable 2IEd-6 4.B. Levels of Activity
.
3.14. Fire Detectors 740s
.
' ~
3.15 . Seismic Monitoring Instrumentation 240u
.
3 .15 Seismic Monitoring Instrumentation Surveillance 240v Requirements
. .
.
.
_
.
__
-
.
-
. l
.
.
.-
( -
: .
-
- /
.
\ .
. .
. _
.
.
..
.
.
.
.
Amendment No'. YG2, IM 107 /111 vii 3/.19/85 . .
.
. .
.
.
.
.
. . . . - .
~ . . . . - . ...
- - - = _ . .
, . . _ .
- - - - - - - _ . - _ _ _ _ _
.
M ME RUDG'IQwly f
l l i I l l I
..
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ .
PBAPS g[ LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT PROTECTIVE INSTRUMENTATION _ PROTECTIVE INSTRUMENTATION Applicability: -Applicability: Applies to the plant in- Applies to the surveil-strumentation which initi- lance requirement of the ates and controls a pro- instrumentation that ini-tective functio tiates and controls pro-tective functio Objective: Objective: To assure the operability To specify the type and of protective instrumenta- frequency of surveillance tio to be applied to protec-tive instrumentatio Specifications: Specifications: Primary Containment Primary Containment Isolation Functions Isolation Functions When primary containment Instrumentation shall be integrity is required, the functionally tested and (( limiting conditions of calibrated as indicated in operation for the instru- Table 4. mentation that initiates primary containment isola- System logic shall be tion are given in Table functionally tested as in-3. dicated in Table 4. Core and Containment Core and Containment Cooling Systems - Cooling Systems - Initiation & Control Initiation & Control The limiting conditions Instrumentation shall be l for operation for the in- ~ functionally tested, cali-strumentation that initi- brated and checked as in-ates or controls the core dicated in Table 4. I
'
and containment cooling systems:are given in Table System logic shall be 3.2.B. This instrumenta- functionally tested as in- 1 tion must be operable when dicated in Table 4. ! the system (s) it initiates 1 or controls are required to be operable as speci- i fied in Section l
,
l-57-APRIL 1973 _ _ . - .
. ,
PBAPS LIMITING CI)NDITIONS FOR OPERATION SURVEILLANCE RECUIREMEPTTS Control Rod Block Actuation Control Rod Block Actuation The limiting conditions of Instrumentation shall be operation for the instru- functionally tested, cali-mentation that initiates brated and checked as indi-control rod blocks are given - cated in Table 4. in Table 3. System logic shall be func- The minimum number of oper- tionally tested as indica-able instrument channels ted in Table 4. specified in Table 3. for the Rod Block Monitor may be reduced by one in ene of the trip systems for
-
maintenance and/or testing, provided that this condi-tion does not last longer than 24 hours in any thirty day perio .
( )
-
.
i l l l
!
i-58-Amendment No. 102/104 December 31, 1984 l l
'
__
_ _ _ _ - _ _ - . _ _- , . _ _ _ _ __
> -
_
'
i
. '
PBAPS LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE REOUIREMFFTS - 3.2.D. Radiation Monitoring Systems-Isolation and 4. Radiation Monitorino Systems-Isolation and Initiaticn Functims Initiation Functions Reactor Building Isolation _and Standby Gas Treatment React'or Buildino Isolation System and Standby Gas Treatment
System The limiting conditions for operation are given in Instrumentation shall be functionally tested, cali-
~ Table 3. brated and checked as indi-
! i cated in Table 4. : System logic shall be func-tionally tested as indica-ted in TEble 4. Drvwell Leak Detecticn Drywell Leak Detection The limiting conditiens of operation for the instru- Instrumentation shall be nentation that mcnitors calibrated and checked as 1 indicated in Table 4.2.E.
.,
' ' ( drywell leak detection are *
given in Table 3. ;
.
.
.
l l ,
!
,
l
l
, i g-59-
, Amendment tio. 102 /104 otcember 31, 1984 I _____ _ _ _ _ . _ _ _ . _ _ _ _ _ . . _ _ . - ~ . _ . _ _ _ . _ _ . . . - _ _ _ _ , - _ _ _ _ _ PBAPS , f l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS Surveillance Informatio Surveillance Information /I ) i
'
'
~ ~ ~
- Readouts " Readouts The limiting conditions for Insirumentation shall be cali-the instrumentation that brated and checked as indicated ,
provides surveillance in- in Table 4. l formation readouts are given in Table 3.2.F.' i i Recirculation Pump Trip Recirculation Pump Trip The limiting conditions Instrumentation shall be for operation for the functionally tested and instrumentation that trips calibrated as indicated ,
'
the recirculation pumps on Table 4. ) as a means of limiting the consequences of a failure System logic shall be func- I to scram during an antici- tionally tested as indicated pated transient are given in Table 4. l
'
in Table 3. i
,
l l
!
.
APRIL 1973 -60-i
. . , . . . - _ _ . . _ . . . . . _ , . - _ . _ _ - _ _
-
,
,
.
IOEhg_3.2 0 Unit 2
>N INSTRUMENTATION TIIAT INITIATES PRIMARY CONTAINMENT ISOLATION E
M-o _ _,____ =______
-W M ,i n i m u m R o_ _. _ _.._ _ _ _ _ _ _ = _---______--__________________________________________________
52 of Operable Number of Instrument CP Instrument Instrument Trip Level Setting Channels Provided Action
* h Channels per By Design - -
Trip System (2} R (1) w , y ___________ . _ _ _ _ _ _ _ _ . _-- - -- - - - - -
-
-- .______________ ____ ._________
2 (6) Reactor Low Water > 0" Indicated 4 Inst. Channels A Level Eevel (3) 1 Reactor High Pressure f 75 psig 2 Inst. Channels D i (Shutdown Cooling 7, Isolation)
:
2 Reactor Low-Low-Low at or above -160" 4 Inst. Channels A Water Level indicated level (4) 2 (6) High Drywell Pressure 3 2 psig 4 Inst. Channels A 2 High Radiation Main j 3 X Normal Rated (8) 4 Inst. Channels B Steam Line Tunnel Full Power Backgroun8 2 Low Pressure Main > 850 psig (7) 4 Inst. Channels B Steam Line 2 (5) Illgh Flow Main 3 140% of Rated 4 Inst. Channels B Steam Line Steam Flow , 2 Main Steam Line f 200 deg. F (9) 4 Inst. Channels B Tunnel Exhaust Duct Illgh - Temperature
*
r
. %
w ___ __ __ _ _ ___ ______ _ __ _ _ ____ _ _ _ _ _ _ _ _
-
__
Unit 2 TA Hl.10 1. y 77 N4 INSTRITMEtTTATIOtt TilAT ItitTI AT!?S PRTMARY ColiTAINMENT ISOLATIOff dR 8;a A Minimum fl of Operable P instrument Instrument Trip Level Settino Number of Instrument y Channels per Channels Provided w Trin Svotem (1) ny Desiqn Action (2) C..; -- b 2 Main Steam Line < 700 den. g Leak Detection Iliqh 4 Inst. Channels O Temperature 1 Reactor Cleanup System Illqh Flow
< 300% of Rated 2 Inst. Channels Plow C 1 Reactor Cleanup ~( 200 deq. P System Iliqh 1 Inst. Channel E
u Tempe ra t u re I a
h
.
m%
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ __ . _ _
. o
.
.
TAllLl? 3. Unit 3
.
N k INSTRUMENTATION TilAT INITIATES.PHIMARY CONTAINMENT ISOLATION R 5 - ' - - ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~
--~~~~- ------------------ -
RT TE-~~R . - - - - - - - - - -
~T of Operable Number of Instrument ~w Instrument Instrument Trip Level Setting Channels Provided Action get channels per By Design (2)
G Trip System (1)
-
= _ _
-- __
--_-_____
, __ __
6$ Reactor Low Water > 0" Indicated 2 (6) 4 Inst. Channels A h Level Eevel (3) , u ,
>
1 Reactor High Pressure j 75 psig 2 Inst. Channels .D i (Shutdown Cooling
$ .
Isolation) , , i . 2 Reactor Low-Low-Low at or above -160" 4 Inst. Channels A Water Level indicated level (4) . 2 (6) High Drywell Pressure j 2 psig 4 Inst. Channels A 2 High Radiation Maln -< 3 X Normal Rated (b) (10) 4 Inst. Channels B Steam Line Tunnel Pull Power Background 2 Low Pressure Main > 850 psig (7) 4 Inst. Channels B t Steam Line - 2 (5) High flow Main j 140% of Rated 4 Inst. Channels ., B , Steam Line Steam Flow 2 Main Steam Line j 200 deg. P (9) 4 Inst. Channels D
Tunnel Exhaust a Duct liigh Temperature
.
, i
, -
_ _ . _
- _ _ _ - _ - - . _ _ m . - _ . - ,___ , .
Unit 3
.
IA_IJi_.f? 3 ),
. , , A, TilSTilliMEffrATIOtt TilAT IllITIATES PillMAftY cot 1TAINMEffr ISOI.ATIOli uN
> b ha wg
-
Minimum No, d of Operable g Itintrisment Instrument Number of Instrument
*
Trip I,evel Setting Channels Provirteel Action Channoin per ny Dealqn
$ Trin System (1) -
(2)
, d'
~
o
" 2 Main Steam f.Ine ~
< 200 eleq . Innt. Channels II I,cak Detection lilqh Temporature
.
1 Iteactor Cleanup < 100% of Haterl 2 Innt. Channels System tilgh Plow C Flow
, 1 Iteactor Cleanup ~< 200 deg. P 1 Inst. Channel E System liigh $ Tempe ra t u re w
I
.
o e
!. .
S t .
.
Unit 2
.
PSAPS NC*TS POR TABLE 3. .
..
' Whenever Primary containment .
3.7, integrity is recuired by Section there each functio shall be two operable or tripped trip systems for If the first systems, column that cannot be met for one of the trip action listed below shall be taken: trip system shall be tripped or the appro ~
. Initiate an orderly shutdown and have the reactor in *
Cold Shutdown Condition in 24 hour Initiate an orderly load reduction and have Main Steam Lines isolated within eight hour Isolate Reactor Water Cleanup Syste Isclate Shutdown Cookin Isolate Reactor Water Cleanup Filter Demineraliters unless' the following provision is satisfied. The RWCU Filter Demineralizer may be used (the isolation . overridden) to route the reactor water to the main condenser trip inoperableor waste fo: surge tank, with the high temperature inlet temoerature up to 48 hours, provided the water confirmed to be belowis monitored 180 degreesonce T. per hour and 3.
. Instrument Zer setooint correscends to 538 inches above vessel ( Instrument setpoint corresponds to 378 inches above vessel l zer . Two recuired for each steam line'. l These containment signalsisolatio also start SBGTS and initiate secondary 7.
' Only recuired in Run Mode (interlocked with . Mode Ssit:h). At a radiat:on level of 1.5 times the normal rated power background, alert an alarm will be tripped in the control room to steam line tunnel radiation level.the control room operators to an increa 9.- In tunnelthearea,event of a loss of ventilation in the main steam line temperature setpoint may be raised upthe main steam line tunnel exhaus to 250 degrees F for a period not toflo ventilation exceed 30 minutes to permit * restoration of the shall observe control room indications of the ductDuring the 30-mi temocrature so in the event of rapid increases (indicative of a steam line break) main steam.line isolation valves.the coerator shall pecmptly close the ! Amen: cent .No. 22, ja: , -63-
111/115 10/2/85 I
) - _ - - _ -
_ - _ . _ _ _ _ . _ _-_ . _ . _ _ . . . _- __
__ - 4 T8 H l.E 1. I tis 1'p t t M r t:1 ATI Ot1 T il A T IrlI T I ATES Olt cot 3 TD o f.S TIIE CoH E A'lO COr3TAIrf MC*4T CODI,i ttri T.YSTF,MS '
?I sa . . _ _ _ _ _ _ _ . . _ , _____._ ______ - _ _ _ _ _ _ _ _ _ _ _
______. _,...__ _ ____ - - . _ _ ,
- - - - - ---_- -
M M i t s t r'u t n *; thimber of Instru-S nt osu r.ilito Trlp I.cVel Setting ment Channels Pro,. Remarks I n s t r isman + Tri p Fitnctiott
= vided tiy Denign ,
P ch innel r; l'o r -
-
g f r,1.[2,.5f g oj - l o n.ict o r I,ne-!.ow t 'i n i n . Indicated <4 Itre t C Reic Initiateo IIPct r,pcIcl 5 7 Inst. Channels
" w it er f.n ve t level -
1-160 in. indicated il Core Spray C In conjunctLon with 2 R ea ct.a r Low-!,ow-1.ow- Low Reactor Pressure
[f (4) RilR In strumen t Water Irvel level Channels initiates core ' spray
*
$ ,
. and LPCI 14 ADS Instrument *
'
$ . Channels
@? In conjunction with
~T confirmatory low level liigh Drywell
' Pressure, 120 second time delay and LPCI or Core Spray pismp interlock initia tes Auto Olowdown (ADS) Initiates startinq of Diesel Generatorr j
.
%
o
-
- . .
-
. _ __ _ _ _ _ - . . . _ . . . - _ _ _ _ . - _ . . _ . . _ , . . _ . . . - _ , , ,
_ _ .,m ,
'
.
Unit 3 P3APS s s NCTES FOR TA3 I 3. _ *
.
.- Wheneve: ?:imary containment
,
3.7, integrity is :equired by See:ien there each functio shall me :wo operable or ::ipped ::ip systems for If the first systems, column cannet be met for one of the ::ip that trip system shall be ::ipped or the 2pp:cpriate ac: ion listed below shall be taken:
' Ini:iate an orde:1v shutdown and have the rese:or in Cold Shu:down Condition in 24 hour .
Initiateisolated Lines an orderly within loadeightreduction and have Main S eam hour _ . Isola:e Reactor Wa:er Cleanup Syste Isola:e Shutdown Coolin . Isclate Reactor Water Cleanup Tilter Demineralizers unless the following provision is satisfied. The RWCU Til e: De=ineralizer may be used (the iscla: ion over:idden) to route condenser or waste surge the reactor water to the main tank, with the
::ip inoperable for up to 48 hours, pro'v.hi:h idedtemperature the water inlet temoe:ature ecnfirmed to be belowis 130 monitored degrees onceF. per hou: and
- .
; Instrument setpoint corresponds to 539 inchas above vessel zer '
- Instrument setpoint {
corresponds to 378 inches above vessel zer . Two re:uired'for each steam lin . These containment signals isols: alsoio start S3GTS and initiate secondary Only required in Run Mode , ,
(interlocked with Mode Swit:n).
At a radiation level of 1.5 times the normal rated power background, an ala:s will be tripped in the control room :o alert the control room operators to an increase in the main steam line tunnel radiation leve . In the event lof a loss of ventilaItion in the main steam line tunnel area, the~ main steam line tunnel exhaust duct high temperature serpoint may be raised up to 250 degrees F for a ventilation flow. period not to exceed 30 minutes to permit' restoration of t shall observe control. room indications of the ductDuring the 3 temperature so in the event of rapid increases (indicative of a steam line break) main steam line isolation valves.the operator shall promptly close the Amendment No. f[' Jetf -63-111/115 10/2/85 . _ _ _
- ,,_ _ _ , . -- . - _ _ - - - . ~ . . - - - _ - - - _ - - .
-.
Unit 3 PBAPS [ NOTES TOR TABLE 3. 2. A (Cont.) ~
(
10. Within 24 hours prior to the planned start of the hydrogen injection test with the reactor power at greater than 20t rated power, the normal full power radiation background level and associated trip setpoints may- be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours of re-establishing normal radiation levels af ter completion of the test program, and within 12 hours of establishinh reactor power levels below 20t rated powe f
~
,
,
,
(f i
!
-
-
I
.
.
s b Amendment No. 104/108-63a-2/7/85 ,
!
,
I __, . - _ . ._ ._
-
. . _ . _ . . ~ .
'
? ,
' .~ _
l TAnI.E J. ~ i tin tp flMEllT ATI Off TilAT IfflTI ATES Olt CDPJTROT.S Tile Colt E AND cot 3TAINHC*1T .
*
.
COOT.IrlG fiY'iTCM , N
:
k o Mi niruin t; < liitmber of Instru-
nt Osmr.ittle ment Channels Pro,- Remarks
- 5 Instrisment Trip Ftanctiott Trip f,cyc1 setting vided by Design x *
,
Channels: Pe r e Ir_it!_ lint _a231 _ , e 2-ta ll in. Inelica teil ta IIPCI C RCIC Initiateo llPCI C RCIC l 5 7 ric.ict or t.ow-Low Inst. Channels
* W.itor T.nyc1 Invel
'
.
4 Core Spray C 1. In conjunction with 2 Reactiar Low-l.ow-Low _ t-160 in. Indicated ItllR Instrument Low Reactor Pressure
[ Hater Level level ('O initiates core Spray
'
, Channels $ ;. .and LPCI * -
14 ADS Instrument ' . e e Channels 2. In conjunctLon with
,
g
i ~
~
p . con Elematory low level liigh Drywell
'
Pressure, 120 second .
,: time delay and LPCI
!! ' .
'
,
or Core spray pinnp interlock initiates Auto niowdown (ADS) 3. Initiates startinq
! i of Diesel Genieratort 9 ' .
, 1 == A 9 ' li . p
w
*
*
.
~
.._
c, 6 .
. .
*
\
-
* *t > %%,a-
.___ ___ _ ____________________ _ _ _ - _
,
,
l
,. -
/
d
,
b
. ,
s ......
.
.
(
nIIS PAGE LEET BLANK DTTENTIONAILY L.>...
.
e
. . , . - +
y
~
e
0 I
& <- , , m , O , 4.. _. .. . . . . - .. . . . . . .. . . _ . .
Y y . * e o
. .
.
.
.
..
.
.
.v m
9
O W<
., ? -
.
.
, e
, * . ,I k
i k3 8I 3 TABLE 3.2.h lCONTINURD) INSTRUMENTATION TilAT INITI ATES OR CONTROLS THE CORK AND CONTAINH8NT CDOLING SYSTEMS I
,
hinleue N *
Of Operable Number of instru-Instrument TrlP Punction Trip Level Setting ment Channels Pro Remarks m Channele Per vided by Design w , g Trip systeet1) _ , n
'
2 Reactor High Hater je45 in. indicated 2 Inst. Channels Tripe HPCI & RCIC Level levet purbines 1 Reactor Low Level 2*312 l'n. above 2 Isot. Channele Prevents inadvertent finside shroud) vessel sero (2/3 operation of contain-core height l sent spray during accident condition.
' 2 containment High 1 < p < 2 pelg 4 Inst. Channels Prevents inadvertent Pressure operation of contain-i 4 ment spray during accident condition.
,
'
1 Cont treetory 1.ow 2*6 in. Indicated 2 Inst. Channels ads Permissive g Level level -
2 High Drywell i 2 pelg 4 Inst. Channele 1. Initiates Core Spray: Pressure . LPCIsHPCI 2. Initiates starting of Diesel Generatore 3. Initiates Auto slow-down (ADS) in conjunction
. with Low-Low-Low teactor - :
4 . water level, 120 second time delay, and
. LPCI or Core Spray pump runnin . .
- _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ . _ _ - _ _ _ _ _ _
TABLE 3. 2. D (Cont 'd) INSTI<UMENTATION TilAT INITI ATES OR cot 31!10LS Tile CORE AND CONTAlt1HENT COOLING SYSTEMS Hinimum N of Operable Instrument Number of Instru-Trip Function Trip Level Setting * ment Channels Pro Remarks Channels Per . vided by Design Tr inJystem f1) 2 Reactor Low 100-500 psig
4 Inst. Channels Permissive for opening Pressure core Spray and LPCI Admission valye Coincident with high dry well pressure, starts LPCI and Core Spray pump Reactor low 200-250 psig 4 Inst. Channels Periaissive for closing l Pressure
, Becirculating Pump Discharge Valv h 1 Reactor Low . 505P575 psig 2 Inst. Channels In conjunction with PCI e
Pressure signal permits closure
* of EllR (LPCI) injection valves.
l
.
.
1 -
,
.
Arendment N /67 (5/5/80) -.
~2 -- _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
-- _ _ - _ _ . . . . _ - - - - .
,
f i -~ _ , TABLE 3. .
k INSTRUMENTATION TilAT INITI ATES OR CONTROLS Tile CORE AND 00NTAINMENT COOLING SYSTEMS l * E i R Minimum N * ROf Operable 2 Instrument Trip Function Number of Instru-Trip Level Setting ment Channels Pro- Remarks i
,
PChannels Per vided by Design
, Trip System (l) ,
la .
$ 2 Core Spray Pump 6 +/- 1 sec 4 timers In conjunction with loss
_, Start Timer 10 +/- 1 sec 4 timers of power initiates the
,
o, starting of CSCS* pump ! 2 LPCI Pump Start Timer o 5 +/- 1 sec 4 timers
- (Two Pumps)
1 ADS Actuation Timer 90 </= t </= 120 2 timers In conjunction with
- seconds Low Reactor Water Level, i
High Drywell Pressure
$ and LPCI or Core Spray e Pump running interlock,
, initiates AD ADS' Bypass Timer * 8 </= t </= 10 , 4 timers In conjunction with j minutes low reactor water level, j bypasses high.drywell pressure initiation of ADS.
! 2 nllR (LPCI) Pump 50 +/- 10 psig 4 channels Discharge Pressure Defers ADS actuation i Interlock pending confirmation of Low Pressure Core Cooling system operation I (LPCI Pump running i interlock).
2 Core Spray Pump 185 +/- 10 psig 4 channels i Discharge Pressure Defers ADS actuation
'
Interlock pending confirmation of i Low Pressure Core cooling
system operation j (Core Spray Pump running interlock).
i *complet Effective when modification associated with this amendment is _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ -
;
TADT,1; _ 3 . 2 . B (Cont'd) INSTRU?tENTATION T!!AT INITIATE'S OR CONTROLS Tile CORE AND CONTAINMENT COOLING SYSTEMS Minimum N Number of Instru-s me t " Trip Function Trip Level Setting Romarks Channels Per y ded by Dos gn Trip- System (1) ' 1 RIIR (LPCI) Trip NA 2 Inst. Channels Monitors availability System bus power of power to logic moni tor system Core Spray Trip . NA 2 Inst. Channels Monitors availability System bus power of power to logic monitor - * systems.
.
-1 ADS Trip System bus NA 3 Inst. Channels Monitors availability power monitor of power to logic I . system I 1 !!PCI Trip System bus NA 2 Inst. Channels Monitors avaliability $I power monitor of power to logic system ' ^
1 RCIC Trip System bus NA 2 Inst. Channels Monitors availability power monitor of power to logic system .2
* '
, .'
I AM 47 October 10, 1978
^ .. .m %,# . .- - _- .- . _ . .-
_-
- .__ _- - .
- '
TABLI: 3.2.0 (CONTINU1:D) INSTRUMENTATION Ti!AT It!ITI ATES Oft CO!!TROLS TIIE CORE AFID CO!!TAItit1ENT COOLING SYSTEMS Minimum N Of Operable Instrument Trip runction Trip Icyc1 Setting Number of Instru-Channels Per ment Channels Pro- Remarks Trip System (l) vided by Design
'
1 Core Spray Sparger 1 (+ /-1. 5 ) psid 2 Inst. Channels to Reactor Pressure ' Alarm to detect core - Vessel d/p . spray sparger pipe brea Condensate Storage >/= 5 feet above 2 Inst. Channels Provides interlock to
, Tank Low Level tank bottom g i IIPCI pump suction I valve Suppression Chamber </= 5 inches above 2 Inst. Channels Transfers IIPCI pump Iligh Level torus midpoint suction to .
1 suppression chambe .
.
.
Amendment ho. BS, 109 /112 June 10, 1985
.
__ - _ _ _ _ - - _ _ - -
_ _ . .. ._ . --. -_ ._-. . . _ . _ _ _
. - . . _ - _- - - - . . . _ _ '
s TABLE 3.2.B (COllTIllUED) l It!STil0P1EllTATIOtl TilAT IllITI ATES OR CollTROLS Tile COllE AtID COtlTAItit1EtlT COOLIllG SYSTEMS ,
,
i l I l11nimun N Of Operable llumber of Instru-Instrument Trip Punction Trip Level Setting rnent Channels Pro-Channels Per Itemarks vided by Design Trip System (1) l
.
1 ItCIC Turbine liigh 14 50" It O( 2) 2 Inst. Channels Plow 2 ,, . .
.-
.
I seconds
.
1 RCIC Turbine fligh 3 . Inst. Channels
Plow T}me Delay
' 2 RCIC Turbine Com- 1200 deg. P (2) 4 Inst. ]
d partment llall 116 Ins ) 6 RCIC Steam Line 1200 deg. P, (2) 12 Inst. ]
.
Area Tem ' , 2 ItCIC Steam Line 100) p> 50 psig (2) 4 Ins ' * Low Pressure
.
I 1 IIPCI Turbine Steam 1225" I120 (3) 2 Inst. Channels Line liigh Plow ] I IIPCI Turbine Illgh 31 1 seconds 2 Inst. Channels Plow Time Delay * !
.
,
r i
..
. *
.
!
^
hendment No. 100/102., "
, . , , July 2, 1984 -
. . , -
TABI.E 3.2.n (CONTINUCD) INSTRUMENTATInti TilAT INITI ATCS OF CO!1TBOLS Tile CORC AND CONTAII;!'ENT COOIANG SYSTEtis Minimun N of operable Number of Trip Function Instrument Instrument Chhnnels per Trip Level Setting Channela Remarks Trip System (1) Provided by Design 4(5) 11PCI Steam Line 100>p>50 psig (3) 4 Ins Low Pressure 2 11PCI Turbine 1200 deg.F (3) Compartment 4 Inst.)
Temperature )
.)
)
4 IIPCI Steam Line <200 deg.F (3) Area Temperature 8 Inst.) 16 Ins ) u I T IIPCI/RHR Valve ) 2 1200 do (3) 4 Inst.)
Station Area Temperature 1 LPCI Cross-Connect NA 1 Ins Position Initiates annun-clation when valve is not close KV Emergency Bus
.
1 per 4KV , 25%(+5%)of Rated Bus tJndervoltage Relay 1. Trips all loaded Voltage (IIGA) breaker . Fast transfer permissiv . Dead bus start of diese I per 4KV 4KV Emergency Dus 95%(+0%,-10%)of Dus Sequential Londing Permits sequential Rated Voltage Relay (SV) - starting of vital loads - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _-
-- - - . _-
J
.
, TABLE 3.2.B (CONTINUED) - INSTRUMENTATIOff TilAT INITI ATES OR CONTitOLS Tile CORE AND CONTAIN!!ENT COOLING SYSTEMS Minimum N Number of of Operable Instrument Instr ument Trip Function Trip Level . Setting Channels . Ecncrks Channels Per Provided by
- Trip System (1)
,
Design 2 per 4 KV Emergency 60%(+5%)of Rated 1. Trips emergency Dus Transformer Vcl.tage. Test at transfer feed Undervoltage(IAV) zero volts in to 4KV cmer-(Inverse time- seconds (+10%). gency. bu ' voltage) 2. Fast transfer , 1
-
permissiv per 4 KV Emergency Trans- 90%(+21) of Bus former Degraded raEed voltage voltage (ITE) , ,
(Instantaneous)
2: 60 second 1. Trips emergency g- ( 5%) time dela transformer feed * 8 to 4 KV emergency bus, i
-
2. Fast transfer , l , permissiv I 6 second (+5%) 1. Trips emergency time dela transformer feed
,
i
, to 4 KV emer- 1
,
. gency bu ;
2. Fast transfer i permiesiv . safety injec-tion signal , require i I _ _ U
..
Amendmont l'n. 97 / 99 April 11. 1984 __
-
.
*
tan! 1: 3 . 2 . 13 (Cot 1 tit 311ED ) JNSTRtJMENTATIOt1 TilAT It3ITI ATES OR CO!1 TROT,S TitC CORE At1D CONTAItitiEliT COOT,1NG SYSTEt1S Hinimum ti t1 umber of of Operable Instrument Instrument Trip Function Trip I,cvel Setting channels Pomarks Channels Per Provided by Trip System (1) Dr. sign 2 per 4 KV Emergency Trans- 07t(45%) of 1. Trips emergency Bus former Degraded Rated voltag transformer feed voltage (Inverse Tests at 2940 to 4 KV emer-time - voltage). volts in 30 seconds gency bu (CV-6) (+10%) 2. Fast trannfer
,
permissiv .
- :
der - a
*
.
' i
- ,
i a
. -
Amendment fin. 97/99, April 11,1984 . _ _ _ _ _ __- . _ _ __ _ . _ _ _ _ . __ ._ . . . _ _ _ _ , _ _ . . _ . . -, _
*
PBAPS Notes _Qr Table 3. .
? Whenever any CSCS subsystem is required by Section 3.5 to be operable, there shall be two operable trip systems. If the first column cannot be met for one of the trip systems, that trip system shall be placed in the tripped condition or the reactor shall be placed in the Cold Shutdown Condition within <24 hour . Close isolation' valves in RCIC subsyste * Close isolation valves in HPCI subsyste . Instrument set point corresponds to 378 inches above vessel zero, s HPCI has only one trip system for these sensor .
l
..,
.
.
. - l l
. -knendment N I 111/115 Oct 2, 1985 . _ . . , _ __ _ _ - _ . .__ __ __ _ _ _ _ __ _
-
*
.
Tant E ~1. INSTRtIMENTATION TIIAT INITI ATES COfftROL ROD HLOCKS
?I Action In9trument Trin Level Setting Number of Instrumrint $ Minimum N ~
Channels Provided R of Operable hy Design
$ "
Instrument ' Channels Per ,
&~ Trip System 6 Inst. Channels (10)
4 APRM lipscale (Flow ~<(0.66w+47-0.666w) FRP x D
- *
Dissed) M FI,PD (2)
- APRM Upscale (Startun ~<t21 6 Inst. Channels (10)
Mode) . t
.,
4 APRM Downscale ~>2.5 indicated on 6 Inst. Channeln (10)
$ scale 2 Inst. Channels (1)
1 (7) Rod Block Monitor -((0.66w+41-0.66aw)x FRP MJ (Flow Binsed) MFLPD (2)
$. '
12.5 indicated on 2 Inst. Channels (1) 1 1 (7) Rod Block Monitor Downscale neale 8 Inst. Channels (10)
* 6 IRM Downscale (1) >2.9 Indicated on - <> scale R Inst. Channels (10)
6 IRM Detector not in (R) Startun Position R Inst. Channeln (10) 6 IRM Unscale 1100 indicated on scale (4) 4 Inst. Channels (1) 2 (5) SRM Detector not in Startun Position counts /ne Inst. Channels (1) 7 (G)(4) SRM Unscale 110 1 Inst. Channel (9) 1 Scram Discharge 129 qallons Instrument volume l tilqh 1,cVel
__ - _ _ . . _ _ .-__
.
_'
,
:
'
* - PBAPS ,
N NOTES 70R TADLE 3. s
. For the startup and run positions of the Reactor Mode Selector Switch, there :. hall be two operable or tripped trip
'The SRM and IRM blocks need not systems.for each function. and the APRM and RBM rod blocks be operable in "Run" mode, need not be operable in "Startup" mode. If the first column cannot be met for one of the two trip systems, this
, condition may exist for up to seven days provided that
during that time the operable system is functionally tested immediately and daily there'after; if this condition lasts longer than seven days,- the system shall be tripped. If the ' first column ca'nnot be uet for both trip syste:as, the - systems shall be trippe !
, This equation will be used in the event of operation with a maximum fraction of limiting power density (MFLPD) greater ,
than the fraction of rated power (FRP) where: , FRP = fraction of rated th.ermal power (3293 HWL)
,
d MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for all !
* ,
8x8 fue . The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of I
) 1. 0, in which case the actual operating value will be use ~
'
Loop Recirculation flow in percent of desig W is - W= 100 for core flow of 102.5 million Ib/hr or greate Tr,ip level setting is in percent of rated power (3293 MWt).
! 4tW is the difference between two loop'and single loop effective recirculation drive flow rate at the same core flow. During single loop operation, the reduction in trip setting (-0. 66 A W) is accomplished by correcting the flow input of the flow biased Rod Block Monitor (RBM) to preserve the original (two loop) relationship between the RBM setpoint and recirculation drive flow, or by adjusting the RBM settin W = 0 for two loop operatio . , IRM downscale is bypassed when it is on its lowest rang ,
- This function is bypassed when the count rate is 2 100 cp . One of the four SRM inputs may be. bypasse . This.SIU4 function is bypassed when.the IRM range switches are on range 8 or abov .
l i 'The trip.is bypassed when the reactor power is 5 305.. 1 . 'This function is bypassed when the mode switch is'placed in ,
. Ru } -N~ .
Am2ndment !!o. 78/79 ,
__ _ - - .--
-
.
PBAPS h'OTES FOR TABLE 3.2.C (Cont.) If the number of operable channels is 1ess than required by the minimum operable channels per trip function requirement, place the inoperable channel in the tripped condition within one hou This note is applicable in the "Run" mode, "Startup" mode and
" Refuel" mode if more than one control rod is withdraw .
1 For the Startup (for IRM rod block) and - the hn (for APRM rod block) positions of the Reactor Mode Selector Switch and with the number of OPERABLE channels: One less than required by the Minimum OPERABLE Channels per Trip F' unction requirement, restore the ino~perab3 e channel to OPERABLE status within 7 days or place the
- inoperable channel in the tripped condition within the next hou Two or more less than required by the Minimum OPERA 3LE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hou ..
.
Amendment No. EE,91/93 2-10-84 - 74a -
__ _ _ __ l
,
TABIE 3. ,
,
' n RADIATION MONITORING SYSTEMS TIIAT INITIATE AND/OR ISOLATE SYSTEMS
!
{
I Minimum No. of
[ Opera bl e i In s tr ume nt No. of Instrument Channels Trip Function Channels Provided Action , Trip Level Setting by Design (2)
2 Refuel Area Exhaust Monitor Upscale, <16 mr/hr 4 Inst. Channel s A or B 2 Reactor Building Area Upscale, <l6 mr/hr 4 Inst. Channels B Exhaust Moni tors NOTES FOP TABLE 3. . Whenever the systems are required to be operable, there shall be two operable or tripped instrument channels per trip system. I f this cannot be met, the indicated action shall be take ' 2. Action A. Cease operation of the refueling equipment.
j B. Isolate secondary containment and start the standby gas treatment system.
4
?
Amendment No. 102/104 December 31, 1984 * i
! ) .
l Table 3.2.E Deleted l
,
l
. .
l Amendment No. 112/116 11-19-85 -7 6-i
!
~
-.
g
-. - -
a
, TAlti.l; 3. 2. F - StiltVI:II.T.AtlCI: Jil5TlutiICIITATIOll S 111 n i rnum flo . = of Operable F TYPE Instrument I rid i ca t ion w Channels I ns t r uene n t and Itange
- -..-----------------------------------------------------------a-------------------------------------l-- Action ***
b@ neactor trater I, eve l itecorder 0-60" }'d Indicator 0-60" (6) (7)
'e tn 2 neactor Presnure Recorder 0-1500 psig (1) (2) (3)
Indicator 0-1200 psig 2 Dryttell Presntire itecorder 0-70 psig (1) (2) (3) 2 Drywell Teinperature Recorde'r 0-400*P (1) (2) (3) indicator 0-400'r
'
2 Suppression Chamber Water necorder 30-230*P (1) (2) (3) Temperature * Indicator 30-230'P (9) i
-: 2 Suppression Chamber Water Itccorder 0-G00*P (1) (2) (3)
Temperature ** Indicator 0-400* P 2 Suppression Chamber. Water Level Recorder 0-2 f (1) (5) Indicator 0-2 f . 1 Control nod Position 20 volt Indicating )
'
Lights ) 1 Neutron flonitoring
) (1) (2) (3) (4)
Sur1,Ilti-1,I.plu1 ) 0-100% ) 1 Safety-neller valve Acountic or Position Indication (0) thermocouple
*
CEfective when modification annociated with this amendment request is complet **- Delete when mod!Eleation associated with this amendment ' request is eneplet *
* * * tiotes for Table 3.2.P appear on page 7 . - . - - - _ _ _ _ _ _ - - - - - . _ __ .-. . . _ _ -
t PSAPS NOTES FOR TABLE 3. one of these parameters is' i
'
1) ~From and af:er reduced to one indication, the date that contir.ued operation is I the succeeding thirty days unless permissible duringsuch instrumentation is sooner made operabl one of these parameters is
2) From and after the date that room, continued operation not indicated in the control is oermissible during the succeeding seven days unless such instrumentation is sooner made operabl (1) and (2) cannot be met,
,
3) If-the recuirements an orderly shutdown of shallnotes be initiated and the reactor i shall be in a cold condition within 24 hour . 4) These surveillance instruments are considered to be l redundant to each other.
*
5) In the event that all indications of this parameter are be restcred in six l disabled (6) hours, and such indication cannotan orderly shutdown shall be in l the hours reactor shall and be in a Cold a dot shutdown Shutdown condition in six condition in the following (6) i
' eighteen (18) hours, With the number of operable channels less than the i
< 6)
!
minimum number of instrumentation channais shown in Table 3.2.F, either restore the inceerable channel :o a: operaole status within 7 days, or be in at least hot
,
I ehutdown within the next 12 hours.
indicated in the contrcl rocm, 7) If this parameter is notone incoerable channel to either restore a: least least hc: j - coerable status within 4812hours hour cr be in at * ' shu:down within the next l l l If this parameter is not indicated in the control rocm, 5) either restore at least one channel to operable statusshutdown within within thirty days or be in at least hot
the next 12 hour ~ !. 9) A suporession Chamber Water Temperature if there instrument are at channel will be considered operableresistance temperature detec least ten (10) operable and no two (2) adjacent resistance temperature < ! J detector inputs are inoperable.
.
~ !
J
- .
-76-i Amendoent H. B, 93 /95 t
I l 3/33/84
I
_-_ . _ m= ,.
" ' " " " -m -,
.__ _ _ _ _ _ _ _
__ _ . _ _ _ _ _ . _ _ _ _ - ____ _ .- . _ _ _ _ . '
.
,
.
i
.
l i TABLE 3. INSTRUMENTATION TilAT INITIATES RECIRCULATION PUMP TRIP
&
E n ____ __ _ _ __ ..--- -
- _ _ _ _ . ---. _
, __ _ - _ _ _ _ _ _ _ _ _ _ _ _
. Minimum N Instrument Trip Level Setting Number of Instrument
!' y of Operable Action _ Instrument Channels Provided
; .9 N
by Design Channels Per h Trip System
, (1) '
, 1 Reactor High Pres- < 1120 psig 4 u, sure (2) - t i 1 Reactor Low-Low Water > -48 in. Indicated -4 (2) I $ B Level level
.
I .
!
Notes for Table 3. . Whenever the reactor is in the RUN Mode, there shall be one operable trip system for each i parameter for each operating recirculation pum shall be take If this cannot be met, the indicated action
1 . l Reduce power and place the mode selector-switch in a mode other than the RUN Mod i
*
I
.
_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _
- _ ___ . _ _ _ . _ _ _ _ - . - - - __ __ _ -- --
l
TABLC 4. MINIMUM TEST AND CALinRATION FREQUENCY FOR PCIS Instrument Channel (5) Instrument Functional _ Test Calibration Freguency Instrument Check 1) Reactor High Pressure (1) Once/3 months None (Shutdown Cooling Permissive) 2) Reactor Low-Low-Low (1) (3) Once/ operating cycle Once/ day Water Level (7) 3) Main Steam High Tem (1) (3) Once/ operating cycle Once/ day 4) Main Steam High Flow (7) (1) (3) Once/ operating cycle Once/ day 5) Main Steam Low Pressure (1)
*
Once/3 months None 6) Reactor Water Cleanup (1) Once/3 months Once/ day High Flow 7) Reactor Water Cleanup (1) Once/3 months None High Tem Logic System Functional Test (4) (6)_ Freguency 1) Main Steam Line Isolation Vv Once/6 months E Main Steam Line Drain Vv 'i Reactor Water Sample Vv * 2) RHR - Isolation Vv. Control Once/6 months i Shutdown Cooling vv Head Spray 3) Reactor Water Cleanup Isolation once/6 months 4) Drywell Isolation Vv Once/6 months TIP Withdrawal l ' Atmospheric Control vvs.
j Sump Drain Valves 5) Standby Gas Treatment System Once/6 months Reactor Building Isolation _.=
=t, s *
v' :e kmf s
_ _ _ _ _ _
_ _ _ - . _ _ . - _ _ __ . - - - - -
.- .
'
s TABLE 4. _ 111NIMUM TEST AtJD CALIBRATION TREQUENCY FOR CSCS Instrument channel Instrument Functional Test Calibration Frequency Instrument Chcck 1) Reactor Water Level (7) (1) (3) Once/ operating cycle Once/ day 2) Drywell Pressure (7) (1) (3) Once/ operating cycle Once/ day 3) Reactor Pressure (7) (1) (3) Once/ operating cycle Once/ day 4) Reactor Pressure - .
(1) Once/3 months PCIS/LPCI Interlock None
.
5) Auto Sequencing
.
NA 4 Timers Once/ operating cycle None
6) t ADS - LPCI or CS (1) Pump Disch. Pressure Once/3 months None Interlocks , 7) Trip System Bus . Powei Monitors (1) NA
' *
Hone 8) Core Spray Sparger d/p (1) Once/6 months Once/ day 9) Steam Line liigh (1) Flow (IIPCI & RCIC) Once/3 months None 10) Steam Line Illgh 13A riow Timers (IIPCI Once/ operating cycle None and RCIC) 11) Steam Line Iligh (1) (3) Temp. (!!PCI & ItCIC) Once/ operating cycle Once/ day 12) Safeguards Area Illgh Tem (1) Once/3 months None
. .
Amendment ilo. ft., N. Jap, 109 /112 June 10, 1985
'
TABLE 4. 2.n (CONTINUED) III!3Ittutt TEST AMKITITTTATIor PnEOUEtiCY FOn CSCS Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check 13) llPCI and ItCIC (1) Steam Line Lov Once/3 months tione Pressure 14) IIPCI Suction Source (1) Once/3 months Levels None 15) 4KV Caergency Power once/ operating cycle Once/5 years System Voltage None nelays (llCA,5v) * 16) ADS Relief Valves Once/ operating cycle Once/ operating cycle * ' Dellows Pressure , None Switches A 17) LPCI/ Cross Connect Once/ refueling cycle ' y valve Position N/A N/A i .
,
18) 4KV Emergency Power Once/ month Source Degraded Once/ operating cycle None ' voltage Relays (IAV.CV-6,ITC) .
' *
.
.
.
Amend:acnt FN. N. /SA. 109/112 June 10, 1985 -. I
PURPOSELY BLANK
. .
h
,
.
O Id TABLE h. w
w MIND'UM TEST AND CALIBRATION FREQUENCY FOR CSCS Legic System Functional Tent (L) (6) Frequency 1) Core Spray Subsystem once/6 conths 2) Lev Pressure Ccolant Injection Subsysten Once/6 months 3) Centainment Ccoling Subsyste= Once/6 months h) EPCI Subsystem Once/6 =cnths 5) EPCI Subsyrten Auto Isolatien onee/6 months 6) ADS Subsystem Once/6 months i 7) FCIC Subsysten Auto Isolatien Once/6 months $' E 3
"
' S) Area Cecling for Safeguard System Once/6 months
.
M
-
.- -.
.
.
3 TAnr.c 4. hk MINIMUM TEST AFID CAI,IRRATIOtl FREOtIEt3CY FOR cot 3TROr, R0D nt,0CKS ACTUATION
*s ?. .
Instrunent Ftinctional
.o Instrument Channel Instrument Test Calibra tion Check A
h 1) APRM - Downscale (1) (3) Once/3 months Once/ day g 2) APRM - Unscale (1) (3) Once/3 months b 3) IRM - Upscale Once/ day e (2) (3) .Startup or Control Shutdown (2) 4) IRM - Downscale (2) (3) Startup or Control Shutdown 5) *tnM - Upecale (1) (3) (?) 6) RnN - Downseale Once/6 months Once/ day 7) SRM - Upscale (1) (3) Once/6 months * Once/ day 81 ) SRM - Detector Not in Startup (2) (3) Startuo or Control Shutdown (2)
(2) (3) Startup or Control Shutdown Ponttion (2)
9) IRM - Detector Not in Startun (2) (3) Startup or Control Shutdown
, Position (2) <=
10) Scram Discharge Instrument Volume Quarterly Once/ Operating Cycle Y - Illah I.evel NA I,ogic System Functional Test (4) (6) Frequency (1) System I, ogle Check Once/6 montha
.
. _ _ _ _ _ _ _ _ _ - - - - - - - - -
.
a TAflT.E 4.7.D gg-MtIIMlH TEST L CAT.1DU AT int 3 PUC0tInticY PnD itADI ATIOtt IOllITORIt!G SYSTEMS asn E:. I nn t rism ent Punctionaf .
~I ns t rism ent I ns t r arm ent Channels Tent Calibration Check ( 2T
L 50 (1) Once/3 monthe Once/ day
% 1) Def uel Area Exhaust g5 Honi tors - Upscale m^
2E 2) Beactor Bu!! ding Area (1) Once/3 months once/ day gic 5 stem Ftmetional Frequency Test (4 6) m 1) Beactor Duilding Isolation once/6 months . u 2) Standby Gas Treatment once/6 months syste's Actuation
'
'.
-
,
.
b e
_ _ _ . _ _ . _ _ - _ . __ _____. .- - - _ _ _ .
- _ _ . . . . _ ~ . _ __ _. . _ . ._ _ _ _--___ _ _ - _ - _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ . - - -_ .~.- . . . . - _ _ _ _
. .
*
a . i
'
g . .
' '
,
)f TABLE 4. .
=
.o i MINIMUM TEST AND CALIBRATION FREQUENCY FOR DRYWELL LEAK DETECTION J
.
.
a D Instrument Channel j g * Instrument Functional Calibration Instrument Test _ Frequency g .
. -
Check
y 1 @ ) $ 1) Equipment Drain Sump Flow Integrator (1) Once/3 months Once/ day.
j .
. ,
p 2) Floor Drain Sump Flow Integrator (1) Once/3 months Once/ day , i
- 3) Drywell Atmosphere Radioactivity l
.
Monitor (1) Once/3 months Once/ day i l i
#
! .
-
!
i
'
i
,
! !
_ - - _ _ _ _ - _ _ ._
TABLE 4. MINIMUll Tint At:D.CALIDitATION FREQUENEYtFOR SURVEILI.ANCE I!3STRUMENTATION Instrument Channel Calibration Frequency Instrument Check 1) Reactor I.evel Once/G months once Each Shift ' 2) Reactor Pressure Once/6 months Once Each Shift 3) Drywell Pressure once/6 months Once Each Shift 4) Drywell Temperature once/6 months once Each Shift 5) Suppression Chamber Water once/ operating cycle ** Once Cach Day ** Temperature Once/6 months *** F Once Each Shift *** 6) Suppression Chamber Water t.e ve l once/6 months
*
Once Cach Shift e 7) Control Rod Position NA Once Each Shift
$
i 8) Neutron Monitoting (APRM) ' Twice Per lleek Once Each Shift 9) Safety / Relief Valve Position Once/ Operating cycle Once/flonth Indicator (acoustics) 10) Safety / Relief Valve Po:;ition NA* Indicator (therencouple) Once/ month 11) Safety Valve Position Once/ operating cycle Once/ month Indicator (Acoustics) 12) Safety Valve Position NA* Indicator (thermocoupit ) Once/ month
*
Pet form instrument functional check once per operating cycle
** Ettective when modification associated with this amendment request is complet *** Delete when modificatior associated with this amendment request is complet .
Amenil..mnt flo. fB, M , 73, 109/112 ~ anne 10 1985
}
,
-w
i
. '
PBAPS NOTES FOR TABLES k.2.A THROUGH L. . Initially once every month. The compilation of instrument failure rate data may include data obtained from other boiling water reactors for which the.same design instrument operates in an environment similar to that of PBAPS. The failure rate data must be reviewed and approved by the AEC prior to any change in the once-a-month frequenc I Functinnal tests, calibrations and instrument checks are not required when tnese instruments are not required to be operable or are trippe Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calibrations shall be performed evithin 24 hours before each startup or controlled shutdown with a
! ' required frequency not to exceed once per wee Instrument checks 'shall be performed at leant once per day during those periods when the instru, ments are required to be operabl =P This instrumentation is excepted from the functional test defin,itio The functional test will consist of injecting a simulated electrical signal into the measurement channel. These instrument channels will be l calibrated using simulated electrical signal l Simulated automatic actuation shall be performed once each operating ; i cycle. Where possible, all logic system functional tests will be performed using the test jack Reactor low water level, high drywell pressure and high radiation main steam line tunnel are not included on Table L.2.A since they are tested on Table 4. . The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip t system . These channels consist of analog transmitters, indicators and electronic Trip units.
i 4 . .
-S7- > Amendment No. 30/29 Jnnuary 1, 1977
_ _ _ - __ . _ . .-. . _
TABLE L.2.G I
&
r ;E-
-
c :- E@ !*IIII?M* TEST AIID CALIE.:ATIO!! FREQUFl;Ci FOR FtEv'IRCULATION FMT TRIP v r, r to e ! y I.rtru 2nt Channel Instrument Fu ctione'_ Check Calibration Frequency ! Ca N Once/ refueling cycle i l " 'f' F-neter P.igh Pres sure Once/ refueling cycle s I U M s et er Lc.v Vrtt er Level Onec/ refueling cycle Once/ refueling cycle
1
: :E:c Systen Functiorni Test
_ Frequency
:<:i-cu'sticn Fu.t Trir Once/ refueling cycle O
C-C* *e
'
L C t; l
.
,
-
%
.- ! <
PBAP3
* , ! '
k l LIMITING CONDITIONS FOR OPERATION ^ SURVEILLANCE REQUIP.EMENT
' CORE AND CONTAINMENT COOLING iCORE AND COffrAINMENT *
SYSTEMS COOLING SYSTEMS
, Applicability: Applicability:
Applies to the operational Applies to the Surveil- , status of the core and sup- lance Requirements of the pression pool cooling sub- core and suppression pool system cooling subsystems which
.
, are required when the
-
corresponding Limiting condition for operation is in effec Obiectiver Obiective: To assure the operability of To ve.rify the operability the core and suppression of the core and suppres-pool cooling subsys ens sion pool cooling subsys-under all conditions for tems under all conditions which this cooling capabi- for which this cooling lity is an essential re- capability is an essential sponse to plant abnormali- response to station abnor-( ties, malitie bpecification: Specification: * Core Spray and LPCI Core Scray and LPCI Subsystems Subsystems Two independent Core Spray Core Spray Subsystem Subsystems (CSS) shall be Testin operabic with each subsystem co= prised of: Item Frecuency (Two 50%) capacity centrifugal (a) Simulated Once/ Opera-
,
pump Automatic ting Cycle Actuation An operabic flow path tes capable of taking suction
'
from the suppression pool (b) Pump Once/ month and transferring the water Operability to the spray sparger in the reactor vesse (c) Motor Once/tr.onth Operated Valve Operability k
.
'
A..,.
. . . . . _2 . . . .. . . . .. . -124- JUNE 11,1976 .. 3
. _ . . . . . . . .
, ,,
PBAPS
'IMITING CONDITIONS L . -
FOR OPERATION ZURVEILLANCE REQUIREMENTS 3.5.A Core Spray & . 4.5.A Core Spray & LPCI subsystem (cont'd) .. LPCI Subsystem (cont'd) */ '
..
.(
Both CSS shall be operable Item Frequency whenever irradiated fuel is in the vessel and prior (d) Pump Flow Rate Once/3 months to reactor startup from a Cold Shutdown condition . *Each Pump in each loop shall except as specified in deliver at least 3125 gpm 3.5.A.2 and 3.5.F.3 below: against a system head corres-ponding to a reactor vessel pressure of 105 psi (e) Core Spray Header *
-
AP Instrumentation
.
Once/ day
*
Check Calibrate - Once/3 months (f) Operability In accordance check to ensure with 4.5. A.2, that pumps will 4.5.A.4 and start and motor 4.5. operated inject- - ion valves will ope . From and after the date 2. When'it is determined that one i that one of the core core spray subsystem is inoper-spray subsystems is able, the operable core spray made or found to be subsystem and the LPCI subsys- ' inoperable for'any reas- tems shall be demonstrated on, continued reactor to be operable in accordance operation is permiss- with 4.5.A.1(f) and 4.5.A.3 (e) ible only during the within 24 hours and at least succeeding seven days once per 72 hours thereafter provided that during until the inoperable core such seven days all spray subsystem is restored * active components of to operable statu the other core spray
*
subsystem and active 3. LPCI Subsystem Testing shall components of the LPCI be as follows: . subsystem are operabl *Until the required - modification is completed,
*
the loop flow rate test at 6250 gpm against a system head corresponding to a
-
reactor vessel pressure of 105 psig will be performed
" * ' . . to satisfy survgillance requirement *
Amendment No. 87, February 18, 1983
,
, .
, PBA .
- .
,
- ' ' LIMITING CONDITIONS SURVEII; LANCE REQUIREMENTS - .
_ FOR OPERATION Frequency Item .
..
(a) Simulated Automatic Once/ Cycle operating Actuation Test (b) Pump operability Once/l month
.
.
.
.
, .-
*
. .
.
'
l
:
.
.
r e
.
.
t
*
.
,
.
<
.
-
.
,,
a 4-
-125a-4 .
,
.
-
'
j
,
Amentent No. 87, Februacy 18,.1983 )
.
.
l
-. -- .__._ -. . .- _ --- - - . _ . _ _ . -
i i i
,
-
, '
i LIMITDC GH31TIONS FOR OPERATION SURVEILEAICE REQUIRDtDrts
(
'
i 3.5'.A core Spray and LPCI - 4.5.A Core Spray and LPCI Subsystem (cont'd) - Subsystem (cont'd) i ,
. . i 3. %o independent Iot Pressure Coolant Itan . Frequency l ' 2njection (LfCI) subsystems will be
- operable ~with eam subsystem (c) Motor Operated once/honth
!
comprised of: , selve operability t l . s. (mso 33-1/3t) W _ty pups, (d) map Flow mate onoe/3 months t Each IJCI pop shall deliver 10,900 i j b. An operable flor path capable of . i taking suction from the gum against a system head correspon-scqpression pool and transferring ding to a vessel pressure of 20 paig based on individual pep test , the water to the reactor pressure-l
; vessel, and
! c. During power operation the IJCI (e) Operability check In accordance i . system cross-tie valve closed to ensure that with 4.5.A.2, i and the associated valve motor pups will start 4.5.A.4 and i operator circuit breaker locked and motor aperated 4.5. l 1 in the off positio injection valves ' will open Both IJCI subsystems'shall ba operable e enever irradiated fuel is in the reactor vessel, and prior to reactor :
I h \ startup from the Cbid shutocun condition,.. except as specified in 3.5.A.4 and . l 3.5.A.5 belo .
, *
)
'
i 4. From and after the date that one of 4. idhen it is determined that one of l the four LPCI pur:ps is made or ~ the RHR (LfCI) pumps is inoperable l found to be inoperable for any at a time when it is required to reason, continued reactor operation be operable, the remaining LICI l j
-
is permissible only during the pumps and associated ficw paths
succeeding seven days provided that and both core spray subsystens shall i i
& ring such seven days the remaining , be demonstrated to be operable in !
active cor:ponents of the IJCI accordance with . 5.1(f) and j sssystecs, and all active 4.5.A.3(e) with . 24 hours and at ' i conponents of both core spray least once per 72 hours thereafter j sesystens are operabl until the LfCI s e system is restored j c, to operable statu l
-
l l S. From and after the date that one 5. eenen it is detenmined that one of
, IaCI subsystem is made er found the IJCI assystem is inoperable l to be inoperable for any reason, both core spray s&systess and the j
' sostiesed reestor eparation is - remaining LacI subsystem shall be permissible only during the ' demonstrated to be operable within succeeding 7 days unless it is sooner 24 hours, and at least once per 72 ande operable, provided that during hours thereafter until the IJCI such 7 days all active cxuponents of s& systen is restored to operable
, "both core spray assystems and the * * -
statu remaining LPCI s esysten are operabl '
.
Amendment N October 10i 1978 ~
.
ww-,-,,,mv - y,-cr,y,-----m- . ,, w en e w ww i
_ _ - _ . _
.
. PEAPS Unit n
.
*
L1jjlTING CONDI'Q0NS FOR OPERATION SURVEILLANCE, REQUIREME,h"r5 " 3.5. A C,or,e,,Sp,ca_y, e,nd ,L_PCI Subsystem (cont'd)
'
4.5.A Cor,e Sp Subsyst sud, LP,C1 (cont'd)
[l
.
6.~ A11 recirculation pump discharge 6.. A11 recirculation pump discharge , valves and bypass valve (s)[*] shall valves and bypass valve (s)(*) shatI he operable prior to reactor startup be tested f or operability during any (or closed if permitted elsewhere period of reactor cold shutdown in these specifications), exceeding 48 hours, if operability tests have not been perf ormed during the preceding 31 day . If the requiremsats of 3.5.A cannot
*
he met, an orearly shutdown of the
! reactor shall be initiated and the ! reactor shall be in the Cold Shutdown I Condition withia 48 hour . Contaisement Coolig 5. Containment Cooling Subsystem (HPSJW Subsystem (NPSW) : 1. Except se specified in 3.5. . Containment Cooling Subsysten 1 3.5.5.3. 3.5.5.4. and 3.5. Testing shall be as follows:
j below, all containment cooling subsystem loops shall be operable Ites Praguency
'
whenever irradiated fuel is in the reactor vess'el and reactor coolant (a) pump once/monti ( temperature is greater than 212'F, Operability and prior to reactor startup f rom a Cold Shutdown Conditio (b) Motor operated once/munth
,
valve operability (c) Pump Capacity After pump
. Test. Each HPSW maintenance pump shall and every f deliver 4500 3 months.
j
' . spa at 233 psi (d) Air test on once/5 yearu dryuell and , ,
torus headers and nozzle . Froe and af ter the datq that any two 2. When it to determined that any two HPSW pumps are made or f ound to be HPSV pumps are inoperable, the inoperable f or any reasoo, continued remaintag components of the ,
,
reactor operation is permissible only containment; cool $ng subsystems shall during the, succeeding thirty days, be demonstrated 'to be operable
unless such pump is sooner made issuediately and weekly therealte operan,le, provided that during such thirty days all, active components of * Upon the removal of both recircul.ac t the containment cooling subsystem are pump discharge valve bypass val' operabl operability and surveillance c'. /
-
ther*ecirculationpumpdischat( , valves tes require . ' Amendment No. 27, 3J, f 7, 55 . . _
"*
June 15, 1979 i - _ _ _ _ _ _ _ _ _ _ - - _ _ . ._._ _..._- _ _ - _ _ _ _ __ _ _ _ - _ _ _ _ _ _
vumn LIMITING-CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 4, .5..B Containment Cooling 4.5.B Containment Cooling Subsystem (cont'd.) Subsystem (cont ' d . ) From and after the date that 3... When it is determined that any 3 HPSW pumps are made or * any 3 HPSW pumps are in-found to be inoperable for operable, the remaining any reasen, continued reactor components of both contain-operation is permissible only ment cooling subsystems during the succeeding fifteen shall be demonstrated to be days unless such pumps are operable immediately and sooner made operable provided weekly thereafte all remaining components of the containment cooling sys-tem are operabl . From and after the date that When 3 containment cooling 3 containment cooling subsys- subsystem loops become in-tem loops are made or found operable , the operable sub-to be inoperable for any rea- system loop and its associ-son, continued reactor opera- ated diesel generator shal'1 tion is permissible only dur- be demonstrated to be oper-ing the succeeding seven days able immediately and the unless such subsystem loop is operable containment cool-sooner made operable, provi- ing subsystem loop daily ded that all active compo- thereafte , nents of the other contain-ment cooling subsystem loop, including its associated die-sel generators, are operabl . If the requirements of 3. cannot be met, an orderly shutdown shall be initiated - and the reactor shall be in a Cold Shutdown Condition with-in 24 hour HPCI Subsystem HPCI Subsystem The HPCI Subsystem shall be HPCI Subsystem testing operable whenever there is shall be performed as fol-irradiated fuel in the reac- lows: tor vessel, reactor pressure is greated than 105 psig, and Item Frequency prior to reactor startup from a Cold Condition, except as (a) Simulated Once/ opera-specified in 3.5.C.2 and Automatic ting cycle 3.5.C.3 belo Actuation Test
*
APPIL 1973 -128-L
. .
! *
:
.
.
, PBAPS i-
'
l-(
~ ' _ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.C RPCI Subsystem (cont'd.) 4.5.C NPCI Subsystem (cont'd.)
Item Frecuency (b) Pump Once/ month Operability (c) Motor Opera- Once/ month ted Valve Cperability (d) Flow Rate at Once/3 months-1000 psig Steam Pressure (e) Flow Rate at Once/ opera-
'
150 psig ting cycle Steam Pressure The HPCI pump shall deli-
. '
ver at least 5000 gpm for a system head correspond- ,' ing to a reactor pressure
.
of 1000 to 159 psi /
' From and af ter the date that When it'is determined that ,
the HPCI Subsystem is made or the HPCI Subsystem is in-found to be inoperable for operable the RCIC, the LPCI any reason, continued reactor subsystem, both core spray
, operation is permissible only subsystems, and the ADS during the succeeding seven subsystem actuation logic days unless such subsystem is shall be demonstrated to be sooner made operable, provi- operable immediatel The ding that during such seven RCIC system and ADS subsys-days all active conponents of tem logic shall be demon-the ADS subsystem, the ?CIC strated to be operable system, the LPCI subsystem daily thereafte and both core spray subsys-tems are operabl . If the requirements of 3. *
cannot be met, an orderly shut-down shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hour *
\
l April U / AM 49 December 15, 19 S-129-
-. _ .. - . - _-_ . ..
.
I i
..
g i PSAPS SURVEILLANCE REQUIREMENTS t.1MITING CULDITIONS FOR OPERATION 4. Reactor Core Isolation Caoline (RCIC Sub-System)_ 1. Reactor care Isolation Caoline (RCIC Sub-Sy stem [ _ RCIC Sub-System testing shall The RCIC Sub-System shallisbe be performed as follows: operable whenever there Frecuency item irradiated fuel in the reactor vessel, the reactor pressure and Once/ Operating is dreater than 105 psig, .( a) Simulated Cycle i prior to reactor startup from Automatic as Actuatton a C.ild Condition, except 11
.pcetfied in 3.5.D.2 belo Test * , .
Once/ Month (b) Pump Operability Once/ Month (c) Motor Operated Valve Operability Once/3 Months
;' (d) Flow Race at 1000 psig
- e%e I Steam Pressure
. Once/ Operating
*
(e) Flow Race at Cycle r% 150 psig Steam Pressure The RICI pump shall deliver at least 600 gpm for a system head corresponding to a reactor pressura of 1000 to 150 psi . 'When it is determined that the RCIC sub-system is inop- From and after the date-that h ll be the RCICS is made or found ,e,able, r the HPCIS s a to be inoperable for any reason, demonstrated to be cperable
, continued reactor power opera- immediately and weekly there- ,
cion is permissible only during afte ' '
'the succeeding seven days provided that -during such ~ *Shall include automatic restart ,a
{
seven days the HPCIS is operable, on low water level signa . j If the requirements - of 3. cannot be met, an orderly ~ shut-j
'
cown shall be initiated and'
'
l j thc' reactor pressure shall - - Oe reduced to 105 psig w-thin
-
24 hour .
,
-130-100/102
'.aiendment No. -
.h . t 2 , 1984
- - . -
,- .
__ _ _ _ . ___ PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT f 4.5.E Automatic Depressurization
,
3.5.E Automatic Depressurization I
[ System (ADS) ^
System (ADS) The Automatic Depressuriza- During each operating cycle tion Subsystem shall be oper- the following tests shall
- able whenever there is irra- be performed on the ADS:
diated fuel in the reactor vessel and the reactor pres- A simulated automatic actu-sure is greater than 105 psig ation test shall be per-and prior to a startup from a formed prior to startup af-Cold Condition, except as ter each refueling outag specified in 3.5.E.2 belo . From and after the date that When it is determined that one valve in the automatic one valve of the ADS is in-
! depressurization subsystem is operable, the ADS subsystem made or found to be inoper- actuation logic for the able for any reason, conti- other ADS valves and the nued reactor operation is HPCI subsystem shall be permissible only during the demonstrated to be operable succeeding seven days unless immediately and at least such valve is sooner made weekly thereafte operable, provided that dur-ing such seven days the HPCI subsystem is operable.
J I I
- If the requirements of 3. cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 105 psig within 24 hour l l
<
l
l
l
[ .
l l J a n .'9, 1976-131-
.-. - ,, _ _ _ - . . . .-
_ . _ . l PBAPS I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS ( 3.5.F Minimum Low Pressure Cooling 4.5.F Minimum Low Pressure and Diesel Cenerator Coolina and Diesel Availability Generator Availability 1. During any period when one 1. When it is determined that one diesel generator is inoper- diesel generator is inoperable,a able , , continued react or oper- low pressure core cooling and ation is permissible only containment cooling subsystcou during the succeeding seven shall be demonstrated to be days unless such diesel gene- operable immediately and daily rator is s ooner made operable, thereafter. In addition, the provided that all of the low ' operable diesel gene rat ors shall be demonstrated to be i Pressure core and containment operable immediately and daily cooling subsystems and the remaining diesel generators thereafte shall be operable. If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be placed in the Cold Shutdown Condition within 24 hour . Any combination of inoperable ! components in the core and . containment cooling s y s t e ms ( shall not defeat the capabi-lity of the remaining oper-able c onp onent s to f ulfill the cooling function . When irradiated fuel is in the react or vessel and the reactor is in the Cold Shutdown Cond1-tion, b ot h'EWre spray systems, l
' the LPCI and containment j cooling subsystans may be j inoperable, provided no work is being done which has the i potential f or draining the ~ react or vesse . During a refueling outage, fuel and LPRM_ removal and r ep la ce me n t may be perf ormed ,p rovided at _, least one of the f ollowing conditions below is , satisfied:
. --
Amendment No. 65/6L -
- 132-March 26, 1980 -- - . _ - _ _ . - - _ _ _ .
_ _ . - _ __ __ _ _ _
.-- __ - - _
FBAPS SURVEILLANCE REQUIREMENTS _ s' LIMITING CONDITIONS FOR OPERATION t 4.5. (Cont'd) 3.5.F.3 (Cont'd) B oth core spray systems and the LFCI system shall be operable except that one core spray system er the LFCI system may be in-operable f or a period of thirty days, or b. The reactor vessel head is removed, the cavity is flooded, the spent f uel p ool gates are removed, and the water level is maintained at least 21 feet over the t op of irradiated fuel assemblies seated in the spent fuel s t o r.a g e p ool racks and no work is being perf orme d which has the potential for draining the reactor vesse , I '
'
l I t l l
.
O
% e M 4$kI -t32s-l
_ _ - - - - - -
- - _ __ . . _ _ . _ _ _ .i
._ _ . _ _ . .
. _ _ _ . _ _ _
LIMITING CONDITIONS FOR OPERATION l SURVEILLANCE REOPIREMENT (. ' 3.5.G Maintenance of Filled .- 4. 5. G Maintenance of Filled
.{ . Discharge Pipe - - -
,s
- :--- - -' ;- -- Discharge Pipe
-
-
. -. .
- - - - .
. .. '
Whenever core spray subsys- -- The following surveillance tems, LPCI subsystem, HPCI, requirements shall be ad-or.RCIC are required to be ,, hered to to assure that the
. operable,',the discharge' pip - ** disch'a'rge' piping of the ' ~
ing from th'e 'pssp" discharge." -*4' ~
' - ooie spray subsystems,.LPCI of these systems to tiW las6' .W *
3*"s u
~ -- ~~ ' '
E .W "ar'b's'ystem, e' filled *idCI#'And A6 RCIC Dilt'yW .7r'
' ~ ' block" . .:
valve'sfialT
.;: L .: .:. :. s be filledP t. -c.- :.h:t.'b str#uy g v .
~ ~~
~-
l ' Wheneier'th'e M CI'6r RCIC
-
's'ystie'm . is lined up' to take
-
'~
suction frois the t9rus, the
~
~
' discharge piping of the N'2"~ HPCIand RCIC shall be
'
-
vented from the high point
' ~
of the system and water
-
-
flow observed on a monthly
::. basis.* " :=-
'
: .-
2; The level swii:ches which monitor the LPCI and core spray ; Lines,to ensure they ( ',
-
are full'shall'be f6nction-j, ,.[ ally tested evait~o'perating
~
- .
,;, ,' cycle.' ]. * ' } '. . , '-
.
.-
g 3. 5 . ENGINEERED SAFEGUARDS 4. 5 . ENGINEERED SAFEGUARDS COMPARTMENTS COOLING AND COMPARTMENT COOLING AND VENTILATION VENTILATION _ If both unit coolers serving The unit cooiers for each one Reactor Core Isolation of the RCIC, HPCI, Core Cooling (RCIC) , High Pressure Spray, and RHR pumps shall Coolant Injection (HPCI) , Core be checked,for operability Spray or Residual Heat Removal during surveillance testing (RHR) pump are out of service, 5 of the associated pump ~^*- the associated pump shall be"._ .
. . . .
~ .,'
-
considered inoperable fof' .~' J ,' ' . :' 7. ' '" ", l purposes of Specifications
~~
' .
.
- '~ ~
- 3.5.A, 3.5.C, or 3.5.D as
- applicabl ~
I
- .. - [ _F * * APRIL 1973
_ __ _ . . .
,. _
l
'~.,.I~~~'.,,.
. .
.
I
*
,
PBAPS Uni , r,' i SURVEILLANCE REQUIREMENTS ) l LIMITING CONDITIONS FOR OPERATION I
'
3.5.I Average Planar LHGR 4.5.I Average Planar LHGR . i During power operation, the APLHGR The APLEGR for each type of fuel for each type of fuel as a function . as a function of average planar - of average planar exposure shall not
'
exposure shall be checked daily > , exceed the limiting value shown' in during reactor operation at the applicable figures during two >25% rated thermal power.
, recirculation loop operations.
- During single loop operation,-the APLHGR for each fuel type shall
- not exceed .the above values .
-
multiplied by the f'llowing o reduction factor: 0.79 for P8XBR and BPBX8R fuel. .If at any time e during operation it is determined by normal surveillance that the limiting value of APLHGR is being c
- -
exceeded, action shall be initiated within one (1) hour * to restore APLHGR to within
..prescr.ibed limit If the APLHGR is not returned to within .
prescribed limits within five (5) . I hours reactor power-shall be decreased at a rate which would . bring the reactor to the cold shutdown condition within 36 hours unless APLEGR is returned
" to within limits during this period Surveillance and
- corresponding action shall '
-
continue until reactor operation
.
is within the prescribed limit ,,
. .
.
. - ..
.. .. .
'
- ~
-
. .; .
*: , ..
,
p
* - -
.
.
._
3.5.J. Local LHGR ,
~'
4.5.J' Local LEGR
. During power operation, the. lineal
'
'The LEGR as a function of core heat generation rate (LEGR) of'any height shall be checked daily during reactor operation at
-
' - rod in any fuel assembly at' any .
>254 rated thermal powe axial location shall not exceed -
-
design LHG [
-
.
LEGR < LHGRd ,
-
'
- -
:
.. ~
-
. ,
,
LNGRd =. Design LEGR- , .
-
,
~'
.
- * -~
m
. - P.51. 3'13.4,.kW/f t; . tor' _a1118X8 _ fuel.',
-
.. . . , - - - , ,
-
:.- -
..
- -
.
. . . . . , , . . .
.. .. \
.. .. .. .
.
. . ;
. . c -
: l
. . .
. Amendment No. Q. fS. 79. 7E. M.108 -133a-
~
3/19/85 ' _ _ _ _ _ _ _ _ __- ._ _ - ___ _ . _ _ _ . _ - _
_, m -- w . r .--= .. # n- . - -
..gr%=t
~5 %.**,& q r. . . a -N ,' ',. . ..
.
.
_
..
< ?p }-.} -y c .l. .tjn'# *"'h i r? ky h &. CL,
'
'
'" '
9 e ~ * -* ,,*^ .. .
's . neW'.r s s c: 4 -
,,tn'. ~.l J' ~p .y-3* g** n C.;'c ~
. ;[49 O .l y. . , } ;, k; 4? . .- .
. f'_ *c_.... .w. . . _ -- -~ . . . -m. .. '[ . ~. , . ,. _ .. . f, f. .? .E ' f ? & %.<~{. / h . , _ . ; ,. . %. 'y.~}l-;)?~.f
'
*
4; ."%_ 7;. g%.
. , . ,
y, ,- % ,
- '-*u - m
,. .Y . ,. m ....w,M
.
. .as.. rr ger,. q . - ; - . - - _ .
.4 ~ .go .-
9-- ' aJ . 6 - .
-
.. c,,. n $_
- -
.'...*..
; ;4 f . . .% ;Q'.-3
.
--.
- '
' 1 ' . * ' . ' . *
r .i M - >
s ; n : u m,- e : .- 4 #' :-%e (.-'** -
'5 '
f ,g,,.;- T..,y.y.y. ;,' -g -l _ _.. .,
*- ). y -.#.p.ix
-
. .,vxw nm .
.. m - - ., .p*;tp'i,' Ng ' y_J ;La-y .y h e. .--=.. , . _ . . : .
.. .Q' m:.- ~ -
, * ,
'
k *. . .
- .
'
_
. - '.
*
r, N y '. g.-* ; Y .= . ? Tl - R ".f h Y' l;
'
-
. . .; . .p ' 1. ~.' usy ,- - *'
*f?"
-
1% . 9. ; -
~ : _ fc . w . , = :, l.1,. y ; _ . 4 '.%^ ;*..
r ' .- +. .
%,,
n - - , ,
;
k Qt**2.y,b a . % - ,. .
-
. . 9.;: - ;. : ; . . . . ',
.:- , .- y
.-[~ 3 p4A j. -j ;.3 =y .;,g. ....y ,y, 3 ; , , . .:- -I
- .gr ;p
: .. 1 -
&. .
* ..:-
- , , _ , , ; .g c i, ,
- '
( ; , _: , . .
,
.;_.. ; , ; ,. ., .,_R__ . -g ;
,
. ;
1 947 n r.p. g , p; y p .y,. ,. .
,
;
? , . ^,h -h
_ _
..-' f.. ,'. y
,
g A .,.t< { h $ y.. f f ,,7g .. i. ^f. . R f' , < c.. &. l}. j.. -
. .
y.} Q ' * ,
.
4 - ', -' p'.,,,.- '
.
.,
. .g. '.gN,f.. .' x, 7 g y, . ,f 'y
: *%
'. . L f $. . >$.'...~._, , : ._ *
.
: ' .
,' _ . $. ; ,
.: . m' ,
.. r 1'^
ic ' ).
-
.,
.
v- ,
.' , ' . _ ,. ,
-
, ,~ -
.
y ..%. ,.-. g..a _
,
f > g . . .. * .n,. )
.
,.
.s
.e r ,!
_ s ,..-4
-
. . ... . - m
..g< - .
..g , . . , .,3 . , .i , , ,,, -, ' . ,' .; . .,y R- '
.'. ;p _ ,#
.
,,
., , '.i- , u .;,. , . -
. .. . . ;. , m . ., g,. .y_%. .
, .
,
,.. , -
.
.. .
* . ..
,, . . .
-
. . . . ., . , . .
~ . * i. . ,, (k .- %..-..,,4 t.E-F.**.-. . ;.
. -
.
~ ; w- .=e4 . a - , . ., -- , g wi .' - ,,,
.'. ,,
.
J. l /. . .
-
*
# v *t
. r).
. w- 'm . 4,'6.I * ' , '>. ...5a
~ . -
. n- w. ;. >- ' - ,. -
,
U
.
-
,
.. [ . . ,^ h, ', 4 - 4 ., ..h~ " 7 [ k '. 8l . , . gk h 'i ' ,4 <
"
' ,' j.i.c . j\ - [* 5
'3
^"; "'.,',,I
,
!..
,]
e;.. ,j .:, '[' , f &'56 . **',[.'
* * ;
v . . . ' ,' 'l~. ; {
+.
} ; _ .r
. }. _J .. . . -
,s, - v .,, ,, *'.,.,l,'
e ,_
,_ -
,
:
.' **
. ;
g
. , ..s 5 s.x , - -- . . . . . . 2,
, - -
lm.,
,* o ;e :', .. . .y ~
; ./ ' h. . ,, j g :. , a - -
', ; , " . , . . t
. " , . . . ,(.-. ~ . y
, .
*,s~ . . .
' i 71 l . _ , , ,,g ff * * Ey ,y' gM ' .-
,
.
"
>
(. 7 4 .J,., - '- f. y ; .( :.A
,e.+
-
.
.,
[.. - .-
'] . , j
~
* b.* '->k .h
*k., .*
s .. [ ,
, k[ , ' -
,
3 ,. ] ! , $ = [. e n .; * , - ;n r g;~gg n.' -s. ,9+*
'
'
., ar
'
4a'
-
!. ... ..
q. .. ' ,{
.
y.m$ .<' *. =. n. t;.; . . , ': a , .g_js,:,'. . . .
...? . O,- ,
*'., r- 4 r, - e y ; 2
, '; ---*.-% _ _ agi, w '.d . ' ' Age g ' y
. -
.
p
..".', e e, ?
,
, .y,p( A .O,.* '*
. , .% 'gi '..#, %.
'
. [ ;) ..*$ ' ( ,.._
~.m Th, . . . . .+
.+ I
% !-) p. . ,...
.w . a . !'.kW .. 7
J - ,4' -. n-* .. . . .m..?.o. ,... p , . ., . ? %y ,..(
.
%, . . i .
, ,
,%.
[.- '. * . , . ,- >
.
'w ,~' ..
,.
' ..~ z e a , .~
w ww , n-v.~, M * .. ~( ; } ',. .. *
.: _ p ~.-p._(c
..
^
*
,.,. . , < - . .p '... . . rt ', . p-lq- -
,
_ . . . , auf. ' . 4,.-
>' g ; . ,y . m . . .;,.u,, , .y
_ c . . n ,e< - -
- . - . . ..
_
:. -
_
.n~Dy;: C.. . :. ,.w ". : v y..;
;
.s ~ a -:r . , .
. .
. - n . --
.
-
y 4:, , gr ..e... p y
. - -
... , .4 , , _ . , . . .
.
, ,4 _; W, _ :- _ . . .
-
? ,.T -t g s
- [d ' .? . "%
f Q , W : .4,.g . p .
, . ( ' . y.gg.y , ,... ( .;f .g Q y) , . 4 j p , - 4, . ; C~~ h ' i ' * ; rf sg ,$ j yn Q j Q Q.Q.c_p & n.jrgl: , ., v. ;{.g r e[ y k Q.z m, . Q ^ &
.,
. .
. .
.
.
_
'.J # ..?*.
: :. ,
.,-R -. ; .; L i M M . m ;e s vp :. .$(:g g. qg7
- Q : W ' 2- _c g*z j & ( :: ~ . b .~.. . x% ty ~.< ~. ;
y~\ Q; :q\9.;. gK . %3, s -f - Q '+g'_g
-
,. ,. W & g(R Q-)
.
, .
.. . . . .. . .- * -
.er , . ..
- Y , . y^Is ', _i wll -
.
e. . :hf[LWy . . ,; .: ; ; ; gq: ,l N '
.,A- - ' $. hf * . : =~
..
' "
.'
'
.'@.. * e . .
W ' .
,.
4 . . 3 .? ( - lN= i- 'eN > . .+'.n.;E . _ 99 . w ,- . - m :4 .. ; e ;.. f l_ i N .' jl _ly?kT! '- Y .$ l .h Qy%e, :y, g*.
*thl? x
}, . a.. -
,,
L 1 ;b p,O. e ,3 ( ,. M m ; 'a~ Q. ,_@_," ".
.3 .,. a 'L y4.-, . , : .v. w.. , . . f , +, . . , %,4 ;
3 .t'. g .. - 2
,.
-
m .. . ..a, .
: ,c . , . y . , .. .
>
< y af.m ,
y'. -g +y+. . .. <.. o t. 3t... - . . , A c.. . . x
.
,-
.%,,. q >,.w,w, .,s%, % . . . ,.Qo,4 .
.
,
m y y ,o p. ,.-; t . + h+. g . r - .; . a, ,,. . t - ~. ,s . . 3g .& .~..- - -e . gya.y. ,.q n~ytn,,.:.; . u mg3 ~.;v:;.: .. . ... m...e-.- i ;
..%v..b. . - * . e- ..-
-
- - ..ti + .,es=
-
..*4r .- .
% * & e. g- .-..
- .g '+ . . . . --
..- ?. > *% s -
? e L-
.a.y q.%y i .GlX p g W.- ..M
.
x :E_i.;~,g%,. W.- . - .:n.:;_.}.?,.~~-f %e % .B.y' 2 Q p..D :
. s . . . , set , ,..: . u .
-- .
, - , _ . y
' f, . .$ f; .;. .}~.,nf)f ... ,~..g . g '}. 3l., , . . . % , f f ' j.. j ..f. 4 '. ,; _l_. (I_L " Y . ~ .W " f;.55:).(: . - - <
. ~ m t_l.$.v.Ll, .,
.n v , . . .- a . . . . < ~a ,x- ,g'~
. .
.
.~ . / .: , > -
: e> c ,. ..
..
. . . . _ *:, .
..~.?.. .
w e .; ? s <= ~ 8 -
.l c.;-
. .
< ., .
s. , . . . z. 1.. u ;. , . z .,.. ...
.-v. m u .;
-
. ,
. ; . n. . . ,
< ~. .3
.
,- ,'. . .h H .
: ' ' T, , . ' i -
. . . .
g@. " ; ' _ , , . - < y J ;,, ' .R . ' . . '
..
# ' ' ' y I ' , ..q .
, -
..
g.. , .
'(,n ,- . .
.,
.. ..
- "
. 7,'?. *. .* - --
' . . . .
:N '. f ,. .:l
~
lt '. .h , R .
*
-
. .
'
- n . .; ;. -
.-
-
,. . ? ,4 y; .. ? . y f y *: ;. . + e v . ( . _ , s ,,y : ,;-c A'. .' -%e. f s. f . v.4 3 j *J gyj?Q,. g 4 h < . , r . J . ;[
'
-
'~~- = -
, ,
.
. . .
y, .s , {
'
, .,
,
-
,
.
} } ;['k . q
'
; - . l, -
"'.. ( b.. ' .! .. * , -: ) ' *i.,~ ,M.; . ? ':- , , *
."
-
. . ;i
. _ +4,+,.. ,;
:
..
.
,..'.4...
~
. -
, .
. -
.. .
.
.%
.' * n.'.u
,
.
. . .
' , . .,
,
. .: .
A, ' w / gp. .
- ._
_., ,.. , .. .i . ' y, - ~ , ; -
;
.
.
.. g . . - (3 . . ;- <
7. .i' ,,. ,
. G p.- .
O- .f.,..'-X w ..~z- : ; >,".'. .-
.y,
- ., . ., ;
. .:.,~, -:y , . , ,, . -" .,..s,-
.
43 . s3- , y . , , _ r
,, , y, 3, y
, . ', -,{ . g .
c L..- ..g .;
-
;p
,
- '*' '; . ~, .
ff . . . , - . ,- ,
,. . 3 lf .o - . *
1~ * ..A,- y-.
', . ' . - , , . .
w./
,
{ 3, . 7, #
'4.-g. ,, -' ep, f g .. - e 3 .
M-- er,i ' t
.
,
s
.; [. ' ',j
.,. , .. .
?
.. g '.3:...c . }'.'....... = ,
.c . ' *' -
. .. ....', u
. . ' .. ,n p. * v. < ' .x. e. ,.)g: % +6c
...
.. - .. : ...
, i. h -. _' . ~- . . '
.,\'.+,.,.'-
s.- v , %; ;: f.: . g.s . - : .t
- k : '..{ .:
. +.. .; . w : .. . ,
. ,
-
, ,
. ; '.s. a, +m . 4 . . .c s.: , < m {. 1. , . 3. . q x ;' ; :s;.
- -
%.
p , 3 : : . , ; : c
= .,
u u. . v....,:
.
; .
.
: ..
,
..
.
.: .-.:- . . ,
. - .x,,
. ..
s,
.. ,a. c
*.- [
.
' ~. .,
,eW , .g 2 . ,. m e
. , .
. .. .. . , , . .
,, . .
b, ~, _
. . ., '
..,'('
.
-
.
! l . ,[' . , , , . [ , .h * (
*
i['.
* h $ f b
,. .f * -.g
, .
m
.,...g._,s.' n ., ,, , .,.
,
... . -M -.M-
-
3 . w' . -.
. ; .; --
;
c . . + ...u . ,m; g # .,. .
*?
, - ,... < r,, e . .o .g .. a # 4 w
....e lc'
.- ..
^
, .;
N 4.y , .,
*- ' .
~ . ' -'. 1 # , [.. '.
9. l, @f ' m'
.. f.' , b-% ' f ?, , ,L.' w Wm. .~-s.,~ 3.','_ j l} g."- ; ,' ,l' '
.n. '- y' j,
-
i , ,,
*'. Am
.
%.y ,
. . .- - ...>
A > 1..) ~
.% .+s v- .~..-
, .o.'
'
p-
-
<: ;.- .. ;. .:.'..
.i . , -
.
S .1 : , s P , . -
'g ' , ." - .... .:
(9.A- ~ ~v e' '.,,. . y ; - - 7.'s '.% ~ ' 4.' .,.:
', ['
.
f. a t- "
..'...t... .V / -
n- .. . .' ". t e . .= 6 -'
,
- ..f '< mis ,, ,'
..
a - .
",4.. l.g .. .
'-
; j ,.;. - .
t .: - a, . > . ,
.
- 17 3, f',# e i-
, r .T .-
.'f,,*,.i s <
,. -
y. : -
.' a'
- . .. .
+-w.+ :. *,w4. ,...,.1 ,
'
A o %;. (h
- .. u
. .
y .; .
,A Qp
. y :
. 7 7 - -;. , .
}{ p= I;. 2r 4 ; {',] T3. f, 4 ? ..; . -n
-j; -
'. .. + ? .g
.-
'
'
. .
e
'y . .w
.. ; , , , . ,
..n .
e.y sg.. , -
..
y . ; ' % -
' ' ~
Y m.7, ' ' ,,, . ' [I [A .( ~. T l ' =. .:
.c
. .
-
,. +.
:
k(- =. ~ +- l[ ' ,? ...c k . ' 'r ,g .
'.
l ,.;, ;.. ' Sir.m- y;. +. s
.
'
. c , . . - .' ,1 ..
,
- -
:. . ? lr t, L~.u .
j i.'s , ." y .n .. s , ' , w
.-
.. , ,%a _.. .s
_;. 3 .3 a . 4. ;,y j 1 bsw-(., Q ,6.W .} e p n .r
.m - .,. . . p..R >, .. -
. . .
. 4 's M V 1 : M r a p ., 4 5 a;.< @%.s.j M..~:.C,1.@ - : ;+ 4 y n. m v. < f. M .>.-%.4 Q % l.;.~.:.J, 4 ow n.wn A
.
'
p. . - h; $ p j -f (-
.
. - . .. = .. . .- . ..
m mcx.c- .
. _ . . . . .
. .- .
. . . . . . _ . . . . .,
;,~..y .. . . . . .
-
S
.-WV M.TTENCICOND2'!'IONSDDR'bORERA'f10N.'.hh e - u.o - . g a . .u u ;g_~.&." ,
'N . 1 ;,,
.,a .g.;. 4 . . ,
-
. . . , , , ,
- ~~- . , v.-e n n. .. . . . . . ,. :; - .-,.-.-
.
' . - -
.
..-~~.
_ --- r : - t- ._c- - - - , . ~ ~. ._ * ..1 _- g-
--
:. ,kg;g .Nh;N .
., - .
b-
*
$ .*5 :*
$- ;'.)2n.p.?y%.f
:
f n ,-(, . .'.h.gltg.i.. . ?hM &.,&,E&h [.g)
.. yh, ~ --%~=. SUDM&..$. ~ESV , - m'1,f~
.
'..
_
-
%. .- . ' . o..y: -
===~~wc~ -
m . : .; ~. - 1.;.q;- m& m.. m m-: 3 ~. .. , i . . . : *i. .
. - - .. - 3 #. ;n*PM.4'th;;
. . -
r /Cn-: .. ..C.q.,..---
. -
f - _ . .1.. . . ~ . . . Ag' . . a.- m... w(
.
: . w- : . ~.
-
.r. .'s...L.4y;x
.i s, y~. ,. , g,.o ,n~ .: 4s n.ww) ,..:; .. T .
,, . r T.c1 <- .e .7.~7,- . i .c. '.).*r a~.y.~%- %4 --
. .. . .,*g , . .~~,4 +.4..----
. . . s. : ph~.
.
--.., s :.
,-
., . .- .:
2 . . . . . ... . .n.:.,
... . ,f ,
. e. c o . . y . 7. s-.. S. .:.,e. .x g
.
.
.
.c .i4 *s., ..
-- . - - .
- te , * - ,. .
.,
.$ -
5. .p, - .e .... ..
. . . . .
L.--.. .. .. 2 - -- *, .'T + 3 -= ' s-
.. . ~-' -
.
3 . :-.
.
. i . . .. * . h . - :.
.. .' m : ..<....-.A..-
,
- . n.----~'.
;, .-.~:?y:. , ,> . ~ . ?.. . -
, . .
.,
- l q .+ * ,. . ?; .. . .f :2,e ' g? :
;._ p . (_":_ ^) y : .f ~~ ,,-
.
:
. . ,
o _ ; ; .3.~s . .: .), gem;,Q R ky;j T--m., .,, .~
['_; n v..: ,3 1 - y . .
. .
:' . . : . q e : :Y .4 ., .r . 4_ a . ;:. ..
- ._~ . : . ,4. 9 - :: 3. a. ; .
. .
:.y . ~. ^ ' ' ,_~. . ,.
.(9.q, ;ca, _ ^
~ , *- .h.....
.
., .
.e _.m , -
_ y . g. &. ; .,. . ~ :3 o .
.,. . fg&,_ . t ;:. M * .)y:. . .. .,; ,, p.y ,:-, ,-;'
-
.
. . . -
..,
,;> -
~
,
. . . - u p,st. ::1
>
g'.a,s - L Q , n., p% y; < *
. _
.
.
.,
,?
. :, ~.&-*..
Q, . _;3 .,.,~-
.}_ ;_ 3:. -n +
. , a -.:
. l .,s .,. .., ; . ;; .,;. .;. m,;q . _
.> . . ."_ '. -
. u ...' ,- *_- e9 . .'. D
,
,.'t.c%. ~ ,.M.;( _; g. .:. : ; ?, --- --c,. .-- - '.4.- - . . :. 2 : p' ~~ ~ ..Q?' .7 _2*- W. . .h.g C, y '.
-
.m .'
m,_-f..,%,;.:.._,. _.. W,x, . . : c'
.
. _z .
. % '. . .. .. .. .'.:... ;...: y,.t sy. xg G. -. 3. . W . .
.
.
.... w k._.s.,
.
i ,
.
.,. .-
E< -
* #.m . x.j._ .. w.-<,- .
, ....e - . .y .
-
m. . . ..;A n, s:: .,.-
,s -
. . y : .;c g. 4.,. . ' . - .,. . .. :2.3%
..
g. . * .T.. -,..:%. g.d,.. r., :%y f F d,T@. _,; ,hgt ;.;g.uH.-w. . ..L n. y- e
. . .
,, . _$ .m@:r~ 2 . , g
.
;
. ' . .__ y ..- ... _- ". .:. .
.. .
. . . .: .,%. ..
r, .g t
~ s .
,
. % -a ,w c f; k. D l.[ 4y Q } e ? h h_ ::==c Q h 0 _. h & 'C:. - 'l = -
- m;y . ,
f' 4, - - ._ff*Y.h!,f . N x. .; q ',
? >
# :$,a, ..&;-- 4_y -
...
(::
'E q,$.
x' ..W-c... . % .Q w a.,s . 2 . Pi~ k 7, & ,- . n . ] r .Q L
] ~'s!' M ib &. d ' Q ~ :
. ~. .a> = .=r w s a-x- . - . , . - ..
.
: ..:
: m , .. v ., .-~ w m..~ ; - : n w= m ,;.., ; e ; 1+ ., m . - %! . . ., s1 N.r.w mywpv
- u . . .e e
. .. g. -h y~ ~.n. 2; <. .:**: m t ~ns b. :. . ;; - .r'. . 2 .#.%.
_ . me
- r, _n. . c : ;p ~g ,. .=. .a.:. ; .nt; . :- 7 -
-
.
% .... . a, . r
.r . . 1
:: ,n
. . v.L c, .n. v -
.- .;.
w . . . . ..- . . .
. _ . . .- m ~ n._. c ,
. .,:..m &.~ _ ... n__.: r. . . j,, pv ~ . - .-m . . -. .,.
.
, . . ,.
^--.. :., =. , v,.;.n,>y._~. .%a:< - a . , q,. ~
. .
..
;. : % ,. .
. ?.<
.
.
~-..
. .
:...- .. ,.
. .,. . 2 :Haw __y.-;.
. ; .. : -: ..
. 4
_y .r . p
,
.
, ~. , ,,g p-
-
.
-
: ._ .h *
-
n
. h, , .a
_
.. .
-
:. . - - -m - --- ,,,
y C:W_ -. .; _2:.s.M ;k :.x. . _ f :: =,surgase- ,-u y' Q. -. .M-+ , .A M .
.
.: a
.
t. m 3 .m
.
,, . , . . .
:::.z,p err
<.c ur?~ ' -
. M -
: :; -
, . . ' . ;. ;: . - =:- . . .--.w-..,,~. r. . y i:
. . w. -----~. n G.p[T .. . :. . .+"'
*. m.;.. .r: ::= TT : : ' p,. :4 * -
:.> =,Jb .L
. , :.. -:-1 ..
.
, .
y.:.- . , n.s..m..c,:. . s . ., . ,. ...- . . gs, . c.".;.-. . .- ; .-. . w m, . .,.,p
-
.
. .
. . ~ . . ,.. . . s
: - n. Lw s -. . .,M %.. ..-) %
..
+._s
-
;. . ..,
. ;. :n.,. %. y:
p . ,:.
.
.
.. .
.e.. w, .m..-~..y
.-
m
..,; .
:
. . .m .- . . ..y- . ~ ...y
.
%o
.
,
. ..z..%.... . . .
-
,#- ,
. , .,- . , .,.e .... , . . . . . .. .. ,. . . , . 4 . . , .-
) Li G-,0 -l.7. .M,..k.if . . ..( . [f.@, a ,Q .
. . .
.(
'-
var l M '1; n U ; h, n.. 3..:z._ . ' .$ , . >.
. . . ._ c - 'Q
.
a k?.% y,^. p~. y - :5 '. ....- Q.._.{;16 .%
[. f'y .% ,
. ]Q;e; c. . -
~': .. . .c-... y.:g.% ,f:~ m [; .
. . .
. , . . .
c e =q o k- , ..,.g& ' ' . . . ._
~'~-'Q. *-_* _ .,Q _ x K -- -
.x- '
1 ^ * -_:' :
. . '
-
, 'E . * Q.'
..
.R
, .; i :, :, 2. .:m: .%. . ,.w . Q~, . , < , ?..* Q :-. :s .
. . . .
.
7 <-
-e -c::-m- :. . : : n. - .- -- ? . ... .
w'w w'$,s g.tyf)e. 4.c- . . . .. ,, W
. .. . .
--; g':
..
.- ~ :- .g
.t ._ ~-
- -7 w. b :;: ... u. p. . =. .
..:
l ; . gg Qc R4 -----r,---
._ . . y. . - c; . n, . g3;r.y .Q N&.Wh.;
b .. 'Yg h1W?.Q .m. . c .. ..:,. c .,2;'t
.~;. % % ? & ? - [.l.*~ ] $
- - cp.,".,J f. , :;_..3.. .o. ". . . h. , ~
. A -L+ s=~1 &,:,.[ f)
s- w. h. n't.t q. _ o c v
%; .
.
.,
m f =. ; 6 w . ; .
':M. . v_. , $ ._t ~ ; , =4g j . . s g...
_.;,.
.~ .:.,. ,3,
.. :..;... e y nr. .-...;, .
_ %* * * Q .
.
.. . . - ~ -- , a
.
sa p- . .;. , . . .- .A g,
,-. *
p a Q . p ,, ,4' WJC.ff y@@, . , ,pr- - ~
.
%a .gt"CO'm .
,:, I
-
i y - 2., M. , '2, f.. .W w ily - a .. -
- _ C c: ~H. catipn-V M.:. . W Qa.1,T:;' :
~
,
,; . :.;;,.i 4 Q :. :^_ ...=-.s
.
.. - ,. . . .
eg - r ... a J.ifa l *-.lj. Du.,..y; ..y. M6MT . . f j.x "~. ... z. i,. -. r. .~. ..; : ,. c:r . m:rcr.- W y . .
- .. . . , . -
*
-
. g ~.5 r- 1;
. ,'t. Q -'y**. pc
.
" , .,.} .
c e.cne.v ..,:..e, a.... a,._ .. .g"'.2 [, L.W(. ; f,7*.S *, M .. Qv .
. ., . , , .,
. . .
. > . , .
a.,-7 y.q, T,*.y w, u m.,.. .....,g_._wr
- . 4 .: ..3 .. u.c..-o
.
.- .
..
r . .
-
e., . - c A, ..e . . -.. . ~ j . . _ e - ..:+,..;Az g
.;_:.......... , g...,
-
,.,.4,.
.
.. . .,
,
, , . -;3 g. . .
a_ . ,...- . .
,,g w p .
-
a -~
;
-
.
.----m- . . :. . . . , . ,
-
. . ,. 4 . . . V y
-* *
ps ..ma'?%. ;wl;, .; ; .,..: .. ,.,L"w.n . h,( '..W_ , s. ; ': _L,.;.-~..w u.,y . .. ; -* - :' 4 *- '- .; y
- :w : w .. AW m- ..
.
s
.
. c.,.s, ,.g 75.. .
.. .
,y, w.....
-
.- -
, . . :^ ' w:g$& -
. -
Yay a f..e~~=.~
.
3. 9w: g. h,. 3 . . .W* m. =;.p :.y %3
.
' ,d'y se.-wg -
.
. -==~< W:.
p w. Q+.u>.%, r :. N..g
. e d-(.,v a.. e -4:... w? .u - ,,:a,.4 . , .. ..
L . p. m.. ,.;:- . , -._.. n .
.
... : : ,..
., -
, . -
;-- 3.;;yq.,: ,%, .a... .. - v*7:: .. ; 7.o.=e -
-
. 3. g . . :.. 2.-n v
.
g, y. 7 -~ ; $. . a .: ;;g:_ :- ;; f .n . . ga.ukg y e- :u;_ .yg. ~ .
.
m, >n:
=:s.y., .e n
-
,
. .- .... . . . . ~ . . e
. ; W c. > . . . . e. ~ .. . -
y x :::. . : x ~ q :;:. . . +..?3 ..
.
. .* ~ y:
.
3. ;g.~. .m ~:pg9, yy~.u.. . 3.;,. .., ,$i.3.:: gyu ,. . . .-.,<,,**;. . .
,. -
'
*.--.s;. n, ff(4*3 ;.+ ., -g,,g{,- -, . .hy 'F~. .. , .-_.,.yq
.
.
. --
x. T. .g. 4..-- ..:. . . * x 3-'. y ' . . J.m_, - + , y,
-. b, . ~ m.~i :: ';,. '-*
, .
-
, , ., ; '(* { .. :. ..
,
,.. .u
. , . . , .. . :,..- . .y. . - , . , . , ,. aa,; ., .^a.r. :.g
--. ;. . s.n.;.w :; .. . ..*.e , ,p. .g .:
.
. .q y ,.
..,..<....:.. . . ;:. . . c . . . + . .a, }7 ..
-... ; y .e... . . . .-,:..-, . ,:. _ . v .m, ; . . . ,. - .
:
,-e
- .
? .
.
. ; -
.
.
.
, .
. .
',t .-..:;. . f..;. ~,% - ,. :". .u.Z,.Q.}:.;
.., . ':-u...i.~.',.^^ m.- . ;; ,c~,. .'_.'f~m *
'. . " [> . ,:' .". %. .:. .l . . . -M. -,:M.,
'.,. . .. ... . ^- , $... y,. g y .. . d,, . '4 ik
:
..-- . .: w
.
..e.-
-
:
%- -
y-. - . - r -
.. f :--P:. .- ,. p ,. -; . .1
. ,m ,7 ,, g . . .m
,
<....,.
. s . .s.4..gf.. n. .a 5.#.>,. r, . . p .,
:%y .- A. ,. 2.4,..
.
s . ,,
:.y $.:.;.: v.~ p 2
.
.. .
.
,....
*
. .- v . .y% ~J ~ .?- .
- . f-J ., . .
.%. ..
<
, ~..e . _ +,u.g .rz . d. . .g , . . s,,
.
..,.,. .. ssw, ', .. ...;,4'.-.'-
.
O r .. _ ,
?-
" y%
'
' I * '*
'-
he -[. ,
.5 . . '.
'
. s'w ' #., * ". - f. - E. -. , - - - - . . ' - J' . .: - . . w.hu':"f .;.c. - - .. b
-
.
r..p
-
.. a w *g-- ; :t ; '4 h-q.< M ', , . 4
.,
. }r/ -
'
.
:}
~*
.- [
: . . '; . ;. . e '. ,:
ff . 4 *a . ,
}' '~'
. ,. ..g..- ..'.. . . . -
. .- ..,. . * db-
...i..,.,..,.e +
v. :
.c .---%-y., a--..,. ...
w .- , F,g fty* . - ,. . w#-7 -
.
.
. .
.
"4 -, -,
. " 'yg,j -~
' _ ;ifQ,p. - ,:,
'
'
'
. .'
^
. .
A.: : ,s.Jw
,
%.w,g
, , , ;
~ . . .
.,_7-
; .:. %., M 5j - $%., .~ -
.-l7 ,\
,
,,.4:L,s& "-. g.cv.::, [" .. m.3.. 't5.-n
. j .%.g. ,< + - .. . M.:: k 3.:4,. k .6 -
. - . . .
:. .. $ .. . - . - - -
-
'
.
, . . ._ . _l _ . . .{.
* '
-
* '
.
, n s-
.
-
., z..., ,_ -
..
.
_ . ... % _..m y
'
I. . .* , E f = n. ' : &".$h_Y jW%i'Wu'-$h~''.EQ%m::.mn
**
: ,, '..* .~~~
. :. w -
, .,n ,
'
_
=W .a.W_*'.$' "D :-1 W'W_S:~~~ ';)Ta*;G',
_
. - '. . . e .
u- ;T. . O
.
.
,
,
i
. PBAPS Unit 2 1 -
.
.
Table 3.5. .
:. . : t .' r . = .
OPERATING LIMIT MCPR VALUES
*
, FOR VARIOUS CORE EXPOSURES *'
:
*
: :.
-~
..:.c.q:-g.2. ppt;p.;&. ,
-
.::s .r.o: . . . . - a. .v : m
-
MCPR Operating Limit ** Fuel Type For Incremental Cycle Core Average Exposure
.
'
.
. BOC to 2000 MWD /t 2000 MWD /t before EOC
-
. -.. ... Before E.OC.,r... _
_
. . T.o EO P8X8R *** " h. 23 0 6 ;E ". : . 1,29 l
3: 1. . .- i. e .' -
.
. .
.
- -
..
. . ..
.
.
* If requirement 4.5.K.2.a is me .
** These vaiues shall be increased by 0.01 for single loop operatio ;,. : -: t .'t , y :c :. tu n . : . .%!i ?
' -
*** Applicable to all P8X8R fuel bundles including BP8X8R l
. and the P8DRB285. (Reload 5) types. :- :. . ~.
*
.
- ..
-
. .
.
-
. . . .
..
. .
,
. ,, .
.
t.
- . . .
. ,
,
l
,
. i
- -
.
l
. 1 r .
.
.
.
,
. ..
~
.I~
.
. .
. i... . ' *l
' * *
~ * -
. :,
* -
' - -
._,. ,. ,:: : ._ .
. .
5-(. .. .. ..
.. j
-. _ .
.
_
,
. .- .__.._ . . . .. . . - . .. ..
.
.
.
. .
,
Amendment No, p),108 3/19/85 -1338-
~
.
. '
- _ -. - - - - _ _ . _ . _ . . , _ _ - - . . _ .
-
_ . _ . - - _ _ - - . - _ _ - _ . _ - . . _- - . . _ _ . _ _ . - . - _ _ - - . - - _ _
-
.
.
: .
-
.. ... ..
.. ,. .
-
.
-
.
'
PBAPS Unit 2
.
Table 3.'5. .
.
OPERATING LIMIT MCPR VALUES - FOR VARIOUS CORE EXPOSURES *
.
. .
,
MCPR Operating Limit ** Fuel Type For Incremental Cycle Core Average Exposure
*
BOC to 2000 MWD /t 2000 MWD /t before EOC
.
Before EOC To EOC
.
P8X8R*** 1.34 1.41
.
.
-
.
-
. ... ..
'
* If surveillance re'quirement 4.5.K.2 is not performe '
---
. .- -
.
-
. . (
** These values shall be increased by 0.01 for single loop operatior l
*** Applicable to all P8X8R fuel bundles including BPBXBR and the P8DRB285 (Reload 5) .t.ype ,
'
.
.
- . ,
.
-
- . .
.
. .. .
.. .. .. . ;
. .
-
-
.
,
.
_
.. ..
- -
.. . t
.
. .. ,y ..
,
I
:
' ,
. .
,
.
.
.
-
. !
*
-
.. -. i . .
.. . - .. J' . :.~
-
. .. .. -
,
-
, .l.A g l l, ' ' ._,.
*
..c.- T ... -
.
-
'
:.'_
-
'. - ._ . .-'; , "
.-
;
.- . .... .. ..
- -
_
-
_
. .
..
-
.- . : _
- -
.
.
-
. ,
- Anendment No.' 55,103 3/19/85 ~133" . .
,
- _ _ . . - . _ . . _ _ . _ _ - . _ - _ _ - . ._-_ - ,_ . . .
. _ _ _ _ -
UNIT 3 l PBAPS j
,
l
. . (
LIMITING CONDITIONS FOR OPERATION l SURVEILLANCE REQUIREMENT T 1
)
.
'
[I #
3.5.G Maintenance of Filled 4. 5. G Maintenance of Filled
* - ' ( Discharge Pipe Discharge Pipe l
- Wheneve'r core spray subsys- The following surveillance tems,,LPCI subsystem, HPCI, requirements shall be ad- )
or RCIC are required to be hered to to assure that the ! l operable, the discharge pip- discharge piping of the i ing from the pump discharge core spray subsystems, LPCI i of these systems to the last subsystem, HPCI and RCIC l
'
block valve shall be fille are filled:
! Whenever the HPCI or RCIC l system is lined up to take suction from the torus, the discharge piping of the NPCI and RCIC shall be vented from the high point of the system and water flow observed on a monthly basi . The level switches which monitor the LPCI and core spray lines to ensure they are full shall be function-qi allytestedeveryoperati.jk cycle.' .
3. 5 . ENGINEERED SAFEGUARDS 4. ENGINEERED SAFEGUARDS < COMPARTMENTS COOLING AND COMPARTMENT COOLING AND VENTILATION VENTILATION If both unit coolers serving The unit coolers for each one Reactor Core Isolation of the RCIC, HPCI, Core i Cooling (RCIC), High. Pressure Spray, and RHR pumps shall Coolant Injection (MPCI) , Core be checked for operability Spray or Residual Heat Removal during surveillance testin (RNR) pump are out of service, . of the associated pump the associated pump shall be considered inoperable for purposes of Specifications 3.5.A, 3.5.C, or 3.5.D as applicabl .r' .
.
-133-
- ,-- ---
, . - - - - ---
. - , , - . . , . . - . . . . , , . - - , , , _ . . _ , , , , , . - - - . . . . . . . . - , - - - . . , , , ,,_ , ,, ,---.
-_ .-. - - . .. . _ - Unit 3 PBAPS SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 4.5.I Average Planar LHGR _
3.5.I Average Planar LHGR ( , l l The APLEGR for each type of fuel l During power operation, the' APLEGR as a function of average planar i exposure shall be checked daily for each type of fuel as a functionof during reactor
>254 rated average operation thermal planar power at exposul -
exceed the limiting value shown in , the applicable figures during two -
:
recirculation loop operatio l During single loop operation, the l
!
APLHGR for each fuel type shall not exceed the above values multiplied '
.
j l by the following reduction factors:0.83 for 8X8 fuel; 0.71 for 7X7 fuel: 8X8R, P8X8R, and LTA 0.81 for PTA,If at any time during opera- ~' fue tion it is determined by normal sur- . veillance that the limiting value of APLEGR is being exceeded, action (1)
'shall be initiated within one hour to restore APLHGR to within pre-If the APLHGR is not
,
I scribed limits. returned to within prescribed limits l'
(5) hours reactor power within .five shall be would decreased bring the reactor at atorate thewhich cold
*
(
shutdown limits during this condition period." within 36 hoursunless APLHG ance and corresponding action shall continue until reactor operation is within the prescribed limit .5.J Local LHGR 3.5.J Local LHGR 'The LNGR as a function of core ; During power operation, the linear" height shall be checked daily heat generation rate (LEGR) of any during reactor operation at rod in any fuel assembly at any , >254 rated thermal powe ~ axial location shall not exceed
!
l design LHG LHGR < LHGRd
,
-
*
-
l l LHGRd = Design LEGR13.4 kW/ft for all 8X8 fuel l
:
.
.
'
~133a-Amendment No. 33, M $2, 77, 77, 92 M83) I
*'
l
. . ... . _ . . _ . _ _
- .-.
-
_ _ _, _ _ _ , _ _ _ _ _ _ . _ - , _ _ _ . _ , _ _ , .
.-. . . -. _ .- - . - .- .___ . ._ _-. _
.
'
s s PBAPS Unit 3
~ '
f '
(~ T;IMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.5.J Local LHGR (Cont'd) '
If at any time during operation it 2s determined by normal surveillance that limiting value for LHGR is being exceeded, action
! shall be initiated within one (1)
hour to restore LHGR to within prescribed limit If the LHGR is not returned to within prescribed
;
I limits within five (5) hours, reactor power shall be decreased at a rate which would bring ,the reactor to the cold shutdown condition within 36 hours udiess
,
j
'LHUR is returned to within. limits during this period. Surveillance and corresponding action shall *
continue until reactor operation
- is within the prescribed limit .5.K.1 Minimum Critical Power 4. Minimum Critical Power Ratto (MCPR) Ratio (MCPR)
MCPR shall be checked daily 1. During power operation, the HCPR 1. during reactor power operation for the applicable incremental at 125% rated thermal powe ,( cycle core average exposure and Except as provided in Specificat
'
for each type of fuel shall be equal to or greater than the value 3.5.K.3, the verification of ' given in Specification 3.5.K.2 or the applicability of 3.5.K. .5.K.3 times Kf, where Kf is as Operating Limit MCPR Values shown in Figure 3.5.1.E. If at shall be performed.every 120 l
< any time during operation it operating dayu by scram time ' as d.Lormined by norsal testing 19 or more ' control i uurveillance that the limiting rods on a rotating bauiu and value for MCPR is being performing the following:
exceeded, action shall be
The average scram time initiated:within one (1) hour t'o the 205 insertion l' to restore MCPR to within prescribed position shall be: limits. If the MCPR is not returned to within prescribed 7" ave $ 73 limits within five (5) hours, reactor power shall tue decreased The average scram time at a rate which would bring the to the 20L insertion reactor to the cold shutdown
*
position is determined as follows: condition within~36 hours unless , ' MCPR is returned to within limits n during this period. Surveillance and corresponding action shall )Pa ve = I Nili continue until reactor operation i=1 is within the prescribed w I Ni
'
limit i=1
~
where: n = number of surveillance tests performe to date in the cycl b-
.
,----.-r - .~_c- __ -- -,.,,~, . . . _ . _ _
,.-_-__..-_,,._.-,,,--~.,,__m -_._ _ - , . . , _ _ , - _ . , , . - -
.- . -_ __ - - . _ . . - _-
.
-- -w
< s , PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCF. REOUTREMENTS' 3.5.K. Minimum Critical Power 4 .' 5 . K . Minimum Critieni Power ~
[{E1T(MCPF)(dont'd) _H'a't t o (fiCPR)To'n t * d)
* Except as specified in 3.5.K 3, Ni = number of active control the Operating Limit MCPR Values rods measured in the ith-are as follows: surveillance test.
l a. If requirement 4.5.K.2.a is met: The Operating Limit MCPR values
-
are as given in Table 3.5. [i=averagescramtimeto
' the 20!; insertion position l of all rods measured in ' If requirement 4.5.K.2.a is not the ith surveillance tes met:
The Operating Limit MCPR
' The adjusted analysis mean
, values as a function of T scram time (TB) is calcula' are as given in Figures as follows:
' ~
3.5.K.1 and 3.5. Y2.
N1 l Cf - '
[ B = p +1.65 n * '
ZNi / ,
,
i"1 f( Where: Where: !
[ = Iave - 7B p = mean of the distribut for average scram inne 0.90 -7B time to the 20fe posi.ti<
0.710 sec 3. The Operating Limit MCPR valui Ni = tot. ) number of act i v.- . chall be as given in Table 3.5. control rods measured in if the Surveillance Requirement specification 4.3. of Section 4.5.K.2 to scram time
' -
test control rods is not O = standard deviation of the distribution fue average
-
' performed scram insertion time to the 20f4 position = 0. 0 ',3 . .
. .
, i
., ,
*
I :t;:. . . A:nt nclamni Ho, f3
.
l
.-. , - .. - . _ . .
. . _ , - - - - _ . .
__ .--
.
. .
. .
,
[ PBAPS UNIT 3
*
.
TABLE 3.5. OPERATING LIMIT MCPR VALUES' FOR VARIOUS CORE EXPOSURES * MCPR Operating Limit Fuel Type For Incremental Cycle Core Average Exposure ** BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC BP/P8X8R 1.~2 7 ~~1. 2 8' ~ LTA 1.27 1.28 l
. . . , .* (
' * If requirement 4.5.K.2.a is me ** These values shall be increased by 0.01 for single loop operatio .
. -
_
,
l
!
I
-
,
l
.
-133d-
.
N l
.., Amendment tio. A7, 57, 77, 79, EE, 97, l
107, 114(8-23-85) l l l
'
l
' - _ _ ._ . .-_ ._ - _ . _ _ _ _ . , _. _ _ -__ . = - . . . . . . , . PBAPS .
UNIT 3 ,, ( ,
. (
-
TABLE 3.5. . OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES * MCPR Operating Limit Fuel Type For Incremental Cycle Core Average Exposure ** BOC to 2000 MWD /t 2000 MWD /t.before EOC Before EOC To IOC
~
l'.33
~
- - -- 1.40 BP/PSXSR 1.33 1.40 LTA (
* If surveillance requirement 4.5.K.2 is not performe (
** These values shall be increased by 0.01 for single loop operatio .
.
.
i-133e-Amendment ilo. 77 H, E, 707.114 (8-23-35) l i l _ . _ _ _ _ - _ _ . _ _ . _ , _ . .. -. .
'
PBA?S l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQU~EI'-!ENTS 3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Apolicability: Applicability,- Applies.to the operating Applies to the primary and status of the primary and secondary con ainment secondary containment integrit system Obiective: Obiective: To assure the integrity cf To verify the integrity of the primary and secondary the primary and secondary containment system, containmen Scecificaticn: Soecification: A. Primary Containment 1. The ' suppression chamber 1. Uhenever the nuclear water level and te= erature system is pressurized shall be checked once per da acove atmospheric pressure or work is being done which has the potential 2. Whenever there is in-to drain the vessel, dication of re__l.ief valve operation (except when the pressure suppression the reacter is being pool water volume and temperature shall be shutdown and :orus cooling is being es-maintained within the tablished) or resting followine limits except which adds heat o the as specified by 3.7.A.2, suppression pcol, the or when inoperability pool temperature shall of the core spray systems, be continually monitored
,
the LPCI and containment and also observed and cooling subsystems is logged every 5 minutes permissi; ole as provided until the heat addition for in 3.5.F.3 and 3.5.F. is terminate a. Minimum water
volume- 3. Whenever there is indication 122,900 ft of relief valve operation with the local suppression b. Maximum water volume- pool temperature reaching 200*F 127,300 ft3 or more, an external visual , examination of the suppression chamber shall be conducted be-fore resuming power operatio ( 4. A visual inspection of the sup-pression chamber interior, in-cluding water line regions shall be made at each major refueling outag Amendment No. E!, 93 /95 ,.
.
_ ,~ c ~, _ 3/13/84 mm - r
e _
>=- -Ae B.---.4-- 4.-.a - 4644 4- +- -a , c 4e-- e b * J D-R1->hE.-&4L - r.. . ~ .& A 54 4 , _Qg~ a 4 - _e. A.,.. a p, m,,4 ima a
-
>
d j'
'
i i 4 f T * l - ! . >
>
'
n
,
f ! c ! >
, ,. f
t ? I
,
,f k i I I i L r I*
4 i L k r
?
h
,
f i,
,
<
.
Y
*
'
$.
h
!
.I
!
I k I b
! I I
J l kr
-6 I'
r k
,. .
! L
4
l
e
4 b i
-
.
e
!
;
! :
I
,
!, i . ? i e i I f r i i
,
I I '[ ! i F s f
+ t i,
P e !,
k, i l
'
l .. l
,
, t I
ll 4, I t rr-,v--
.,y-9p y 3 g. p g w-y-y- y --wr+--g< g - 6ne=" -w w yWWA=-g ey'ml'wm, -+w 9 op w-t- g -
eng.m%ew 2trew k-ha WC'74 pte h -*'"'-'V' .8't'4-vW# * ~ **'"* E 8PT-
. . - -. '
PBAPS
,
LIMITING CONDITIO!!S FOR OPERATION . SURVIILLANCE P.EOUIREllEilTS 3. Primarv Containment (Cont'd) Maximum averace suporession pool temperature limits:
(1) During startup/ hot standby and run modes, with the suppression pool temperature greater than 95'F, except as permitted below, restore the temperature to less than 95*F within 24 hours or be in hot shutdown within the next 12 hours and cold shutdocn within the following 24 hour (2) During testing which adds heat to the suppression pool, the pool temperature shall not exceed 105*F. Should the pool temperature exceed 105'F, such testing shall be stopped and the pool temperature must be reduced to below the limit soecified in (1) above within 24 hours or be in hot shutdown within the next hours and cold shutdown within the following 24 hour (3) The reactor shall be scrammed from any operating condition if the pool tempera-ture reaches 110*F. Power operation shall not be resumed until the pool temperature is reduced below the limit specified in (1) abov (4) During reactor isolation conditions, the reactor pressure vessel shall be *
decressurized to less than 200 psig at normal cooldown rates if the cool ' temperature reaches 120* l
l . I l
(
Amendment flo.~ H, 72, 93/95 .-165a-3/13/84 _ - _ _ _ _ _ - _ . -- _ _ . _ _ _ . . .~
= LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3. lirimary Containraent 4.7.A Primary Containment i
. 2. Primary containment integrity 2. Integrated Leak Rate Tes ting shall be maintained at all times when the reactor is a. Integrated leak rate tests critical or when the reactor (ILRT's) shall be perf ormed water temperature is above to verify primary contain - 2120 F and fuel is in the ment integrity. Primary reactor vessel except while containment integrity is performing "open vessel" confirmed if the leakage physics tests at power levels rate does not exceed the not to exceed 5 Mw (t) . equivalent of 0.5 percent of the primary containment 3. If the primary containment integ- volume per 24 hours at 4 rity is breached when it is re_ psi qaired by 3.7.A.2, that integrity shall be reestablished within 24 b. Integrated leak rate tests hours or the reactor placed in a may be performed at either cold shutdown condition within 49 1 Psig or 25 psig, the 24 hours, leakage rate test period, extending to 24 hours of retained internal pressur If it can be demonstrated to the satisfaction of those responsible for the acceptance of the contain-ment structure that the leakage rate can be accu- ( rately determined during a shorter test period, the agreed-upon shorter period may be use Prior to initial operation, integrated leak rate tests must be performed at 4 and 25 psig (with the 25 psig test being performed prior to the 49.1 psig test) to establish the allowable leak rate (in percent of containment volume per 24
. hours) at 25 psig as the lesser of the following values: (La is 0.5 percent)
L L t = 0.5 @tm M
- 66-SEP 8, 1975 .
ww2we V
. LIMITING CONDITIOhS FOR OPERATION ' SURVEILLANCE REQUIREMENTS 1.7.A Primary Containment (Cont'd.) 4.7. A b. Primary ' Containment (Cont ' d) .
g
*
where -
.
Ltm = measured ILR at 25 Psig L am.= measured ILR at 4 psig, and Lm< t LI- - fP t ! Lt = ! where Pa " Peak accident pressure (psia) Pt = appropriately measured test pressures (psia)
~
' *
-
c. The ILRT's shall be per-formed at the following minimum frequency:
'
- ' '
'
i. Prior to initial unit operatio . At approximately three and one-third year in-tervals 'so that any ten-
,
year interval would include four ILRT' ' These intervals may be extended up to eight months if necessary to coincide with refueling
,
outag d. The allowable leakage rates , Lmt and Lam, shall be less
- than 0.75 Lt and 0.75 La .
for Ehe reduced pressure
-
tests. and peak pressure l tests respectively.
l
.
t
.N * -
e-167-APRIL 1973 l
-. . _ - _ . - _ _ _ _ _
@l19BFS '
IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
.7.A Primary Containment (Cont'd.) 4.7.A Primary Containment (Cont'd.)
/\ Ye . Except for the initial (, ILRT, all ILRT's shall be performed without any pre-liminary leak detection surveys and leak repairs immediately prior to the test. If an ILRT has to be terminated due to excessive leakage through identified
. leakage paths, the le akage through such paths shall be '
determined by a local leak-
. age test and recorde After. repairs are made, another ILRT shall be
- conducte ...
. If an ILRT is completed but the acceptance criteria of Specification 4.7. A.2.d is
not satisfied and repairs are necessary, the ILRT need not be repeated provi-ded locally measured Icak-
*
age , reductions , achieved by
' repairs , reduce tne con- (,
tainment's overall measured' leakage rate suf ficiently to meet the acceptance criteri . f. Local leak rate tests (LLRT's) shall bo performed on the primary containment
, testable penetrations and isolation valves at a pres-sure of 49.1 psig (except ,
for the main steam isola-
. tion valves, (see below)
each operating cycle, but
. in no case at intervals greater than two year .
Bolted double-gasketed seals shall be tested when- . ever the seal is closed af ter being opened and at
-
least once per operating cycle, but in no case at
- . intervals greater than two
_ year .
. -16 B-APRIL 1973
,
l
_ f
[ LIKITING CONDITIONS 'FOR OPERATION SURVEILLANCE REQUIREMENTS
,
,_ 3.7. A Primary Containment (Cont'd.) 4.7. A.f. Primary Containment (Cont'd)
*/ gr The Main Steamline -isola-tion valves shall be tested at a pressure .of 25 psig
,
for leakage during each 'rc- l fueling outage. If a total j leakage rate of 11.5 scf/hr i for any one main steamline isolation valve is exceeded, 1
, ,
repairs and retest shall be l performed to correct the
.
conditio g. Continuous Leak Rate Monitor C
'
-
When the primary contain-ment is inerted, the con-
-
tainment shall be continu-ously monitored for gross
'
leakage by review of the iner, ting system makeup requirenents . This moni-toring system may be taken out of service for mainte-nance but shall be returned (i to service as soon as practicabl h. Drywell Surfaces The interior surf aces of the drywell and torus shall be visually inspected each operating cycle for evi-
, dence of deterioration. In addition, the external sur-f aces .of the torus below . the water level shall .be inspected on a routine basis for evidence of torus corrosion or leakag .
O
. -169-
,.
. APRIL 1973 . .. -. _ _ - - - -_ . _ _ . - --- -. _- - - _ -
. . _ _ _ _ _ _ -- . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . _ ' ,
LIMITING CDNDITIONS FOR OPERATION SURVEILI.ANCE REQUIREMENTS t 2 3.7.A Primary Containment 4. Primary Containment
! Pressure Supression Pressure Sucoression Chamber - Reactor Build- Chamber - Reactor Build-ino Vacuum Breakers ino Vacuum Breakers Expect as specified in The pressure suppression 3.7.A.3.b below, two chamber-reactor building pressure suppression vacuum breakers and assoc-chamber-reactor building iated instrumentation in-vacuum breakers shall be cluding set poir.t shall be
operable at all times checked for proper when primary containment operation every refueling integrity is require outag The set point of the differential pressure instrumentation which actuates the pressure ' suppression chamber-reactor building vacuum breakers shall be 0.5 + 0.25 psi From and after the date that one of the pressure suppression chamber-reactor building vacuum i breakers is made or found
! to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such vacuum breaker is sooner made operable, provided that the repair procedure does not violate primary containment integrit . Drywell-Pressure Suppression Drywell-Pressure Suooression Chamber Vacuum Breakers Chamber Vacuum Breakers When primary containment is Each drywell-suppression required, all drywell- chamber vacuum breaker suppression chamber vacuum shall be exercised through breakers shall be operable and positioned in the ,
an opening-closing cycle
,,,, once a mont t ;. . fully closed position * - - (except during testing) When it is determined that a , -
except as specified in vacuum breaker valve is 3.7.A.4.b and c, belo inoperable for opening at a time when g One drywell-suppression chamber vacuum breaker may be non-fully closed so long as it is deter-
-170- Amendment No. 24/23
"i;F v . to76
[
PRAPS
- LTMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRE 4FNTS
'~ ,-19 7.A. Primary Containment ,. 3. Primary Containment i ~
mined to be not more operability is required, than 3 * open as indica- all other vacuum breaker S ted by the position valves shall be exer-light _ cised immediately and i every 15 days thereafter until the inoperable valve hau been returncil normal servic Two drysell-suppression Once each operating chamber vacuum breakers cycle', each vacuum breaker-may be determined to be valve shall be visually inoperable for openin inspected to insure proper maintenance and operatfo If specifications 3.7. A A leak test of the dryvell to
.h.a. .b, or .c cannot , '
suppression chamber structure be met, the situation shall be conducted at each re-shall be corrected within fueling to assure no bypass 2h hours or the tinit will % larr.er than or equivalent to one be placed in a cold shut- inch diameter hole exists betwee down condition in an the dryvell and suppression orderly manner, chambe t
, Oxygen Concentration ;
5 Oxygen Concentration t After completion of the startup The primary containment oxygen test progra= and demonstration concentration shall be measured of plant electrical output, the and recorded at least twice weekl pri=ary centainment atmosphere shall be reduced to less than k% oxygen with nitrogen gas during reactor power operation with reactor coolant pressure above 100 psig, except as specified in 3 7. A. Within the 24-hour period subsequent to placing the reactor in the Run mode following a shutdown, the containment atmosphere oxygen concentration shall
, be reduced to less than h%
by volume and maintained in this conditio De-inerting may commence 24 hours prior to a shutdow T _; t- actcber 1973
__ _
,
LIMITING CONDITIO;S FOR O?ERATIO" i SUR'!EILL?.!:CE EIOUIPI".Z.;TS
.
3.7.A Primarv Cont ainment 4.7.A Primo.rv Cen t ai n' .en t 6. Containr. ant Atmoschere 6. Containment Atmosehere I'
.Dilutlen Di lu t'i cn a. Whenever either reactor 'he post-LOCA contain- -is in pcwcr cperation, r.ent atmosphere dilu- * the Pos t-LOCA Containment tion system'shall be Atmosphere Dilution Sys- functionally tested -
tem must b9 cperable and, once per operating capable of supplying cy cle .
' .
nitrogen to either Unit 2 e i or Unit 3 containment for atmosphere dilution if . required by post-LOCA 1 conditions. If this specification cannot be met,the system must be restored to an operable condition within 30 days or both . reactors mus t be taken out of power opera- . ti en . - , b. Whenever either reactor ' b. The level in the is in power operation, liquid N2 storage tank the post-LOCA Containment shall be recorded ((
\
Atmosphere Dilution Sys-- weekl ,_ ,, tem shall contain a mina-mum of'2000 gallons of liquid N2 If this s=ecification cannot be
: .'et, the minimum volume
.i will be restored within 30 days or both reactors must be taken out of .. power operatio c. *dhenever either of the * The containment reactors is in power crf gen. analyzing sys- ' operation, there shall be tem shall be func-at least one CAD system tionally tested twice H2 and O2 analy:cr serv- per week in con-junc-ing the drywell and one tion with specifica-CAD system H2 and O2 ti 6n 4 . 7 . A .5 . The analyze:r serving the sup- oxygen analyrer shall pression chamber on that . be calibrated once per reacto If this speci- 5 month fication cannot be met, I
.
I A,T.encment No. So /g
-
'
., , e -
_ l , Sept. 13, 1979 _- . - - . . . - - - - - . - . _-. . , . - - . -- . - . - . . . - . . . - -
. _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
.PEAFS
*
.
LIMITING CONDITICKS FCR OPERATICS . , SURVEILLANCE'_ R EOUIREMENT S .~
(Cont'd)
~
3. 7. A. 6. (Cont' d) 4.7.A.6.a i I . . the unit shall be in Hot The CAD system B2 and C2 shutdown within 12. hour analyzers shall te tested' tor
-
operability using standard - tottled H2 and 02 cnce per .
. sonth and shall be calibrated once per 6 mcnths. The atmospheric , ,
analyzing system shall be func-
. ticnally tested once per operating ,
cycle in conjuncticn with the specification 4.7.A. Should one of the twc H2 or C2 analyzers serving the 'drywell cr
,
suppression pool be found inoperatic the remaining analyzer of the sarnc
*
type serving the same comparts.ent
-
shall be testd f or operability once per week until the def ective analyzer 1= m de oJerati d. A 30 psig limit is the " maximur- containrent repressurizaticn allowacle using t.be CAD system. Venting via the SEG7 system to this stack aust te initiated at 30 psig follcwing the
, initial peak pressure
, I at 49.1 psi .
.
.
&
i e !
- ,
i
. ' $nenenent No.M M? I /69 ' -173- ,
l l
. . . . . - . . -
;
. . . .. . _ . . ._ ,
- .. _ _
_ - . _ _ _ . - _ . _ , _ . , _ _ _ _ . . __, _ _ _ . . _ _ . _ _ ___ __ ._. . . _ . _ _ _
-_
_
-
PB;JS LI M A T1 ?It; CONDITIONS FOR OPERATIOi4 SURVEILLANCE HEUUJ HEMEN73 3.7. .If the specifications of-3.7.A.1 through.3.7. /' cannot be met, an orderly shutdown shall le initiated and the .. reactor shall be in a cold shutdown condition within 24
. hour .
.
.
..
.
.
.
ii
)
l
. . . -
? I _;79_
-
Amendment No. U, 69 /68
May 16, 1980 l l I I-----_ ~ - - - _ .
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
. - , # , *
3.7.8. Standby Gas Treatment System 4.7.8. Standby Gas Treatment System
.- 1. Except as specified in 1. At least once per operating cycle, '. 3.7.B.3 below, both filte r the following conditions shall be trains of the standby gas demonstrate treatment system and at least two system fans shall a. Pressure drop across the 1 be operable at all times when combined HEPA filters and secondary containment charcoal adsorber banks is integrity is require less than 8 inches of water at approximatley 8,000 CFM b. Inlet heater is capable of providing at least 40 K . a. The results ofe the in-place 2. a. The tests and sample analysis .
cold DOP and halogenated of Specification 3.7. hydrocarbon tests at shall be performed initially approximately 8,000 CFM on and at least once per year HEPA filters and charcoal for standby service; or adsorber banks _shall show after every 720 hours of 199% DOP removal and 199% filter train operation; or halogenated hydrocarbon following significant removal or that filter painting, fire or chemical train shall not be release in any ventilation
{I ,
\
considered operabl zone communicating with the system when it is in operatio b. The results of laboratory b. Cold DOP testing shall be carbon sample analysis shall perfomed after each complete show 295's radioactive methyl or partial replacement of the
#
iodide removal at a velocity HEPA filter bank or after any within 20 Fof3 vst'ef design,# structural maintenance on the 0.5 to 1.5 mg/m3 inlet methyl system housin iodide concentration, 270% _ relative humidity and 21900F
-
or that filter train shall be considered inoperabl c. If gas flow capability of c. Halogenated hydrocarbon refrig-8,000 CFM : 800 CFM can erant testing shall.be performed
, not be provided to a-filter =.t after each complete or partial ' . ,_ , s,, train by th 4 fans, thit replacement of the charcoal filter train shall not be adsorber bank or.after any considered operabl structural maintenance of the system housin d. Testing of gasket seals for housing doors downstream of the HEPA filters and charcoal , adsorbers shall be perfomed i 4 at and in conformance with each ,
i
- I ' tist performed for compliance j with Specification 4.7.8. . June.25, 1975
- .-
PBAPS
.I.I.II.I.Ty_gt1,N,H,1,T,lg,NS f ,
F0,R OPERATTON _ SURVEILIANCE REQUIRF)fENTS
~'
e. A dry gas purge shall be
/ provided to the filters to insure that the relative humidity in the filter systems does not exceed 70% during idle period . a. At least once per operating 3. From and after the date that cyc1.e automatic initiation of one filter train and/or two fans each filter train of the stand'
of the standby gas treatment gas treatment system shall be system is made or found to be demonstrate Inoperable, reactor operation , , or fnet handling is permissible b. When one filter train of the only diaring the succeeding standby sas treatment system 7 days, unless such filter becomes inoperable the other train or fans are sooner. made filter train and one fan shall ogw rable, provided that during he demonstrated to be operable such 7 days all active components limmediately and daily there-of one standby gas treatment system ' after, except that the filter i rain shall he operabl and charcoal tests as described in 3.7.B.2.a and 3.7. B. 2.h a re not require I f Spec i ficat ions 3.7.B.1 and
.i.7.11. .i a re not met , both unit s n sh,ilI tee placed in the cold '
shutdown condition within 24 h..o r 3 and fuel handling operations
.sh.ill be prohibite ,
i; 2 TTS T
. . .
l
! '75a June 25, 1975 i
- l
_ ._ _ _ _ . . _ _ _ _ . . _ . _ _ _ _ ,
! PEAFS LIMITING CCNDITICNS FCR OPERATIOh SUPVEILLANCE RFOUIRE1EN75 3.7.C Seccndarv centainment 4.7.c Seccndary ccntainment ( - Secondary ccntainment Secondary containment surveillant- ,
'
integrity shall be maintained shall te performed as indicated during all rodes of plant ~below: operation except when all : of the fc11cwing conditions a) A preoperational secondary con-are me tainment capability test shall *
*
be conducted after isolating 9 a) the reactor is subcritical and the reactor building and placinj
-
and Specificaticn 3.3.A is either standby gas treatment me system filter train in operatic ' t) the reactor water temperature Such tests shall demonstrate ti,e is belcw 212 Degrees F and the capability to maintain 1/4 inch !
. reactor coolant system is of water vacuum undcr calm wind ,
vente (<5 mph) conditions with a filte r c) No activity is being performed train flow rate of not more than ! which car reduce the shutdown 10,500 ci l
~ margin below that speci:.ied b) Additional testa shall te perf craud in Specificiation 3. 3. during the first cperating cyclo ;
d) The fuel cask cr irradiated under an adequate number of l fuel is not being moved in different envircnmental wind , the reactor buildin ccnditions to enatle valid ! extrapolation of the tast ranult- . ' c) Seccndary containrent capability 2. If S pecification 3.7.C.1 can- tc maintain 1/4 inch of water r nct be met, the unit shall be vacuum under calm wind (<5 rph) / placed in Het Shutdown within ccnditions with a filter train i' * 12 hours and in Cold Shutdown flow rate of not mo re tha n within 36 hcurs, rrradiated 10,500 cim, shall be demonstrated ; fuel handling operations in at each refueling outage prior the secondary centainment, to refuelin core alteraticns, and acti- d) After a secondary ccntainment vic-vities which could , educe lation is determined, the standby the shutdown marg:o shall be gas treatment system will te , suspende operated immediately after the aff ected zones are isolated l from the remainder cf the seccndary containment to ccafir its ability to maintain the ' remainder of the secondary ccntainment at 1/4 inch of l
' -
water negative pressure under . calm wind ccadition ;
.
'
Amendment No. 71 /@ - 76-
- . . - -
-
.
PBAPS ay SURVEILLANCE REQUIRE!1ENTS LIMITING CONDITIONS FOR OPERATION l4.7.DPrimary Containment
.
3.7.D Primary Containment : Isolation valves Isolation Valves i l 1. The primary containment 1. During reactor power oper- isolation valves surveillance ating conditions , all isola- . shall be performed as follows :
-
tion valves listed in Table 3.7.1 and all instrument line 2 ' a. At least once per operating flow check valves shall be cycle the operable isola-operable except as specified ;i tion valves that are power in 3.7. j operated and automatically
- initiated shall be tested . ;* f or simulated automatic ' >
initiation and closure g time b. At least once per quarter: l; (1) All normally open pcwer l' operated isolatien valves (ey.cep t f or the - i main steam line peser-
,
operated isolation
>, valves) shall be fully , closed and reopene ,
g gj (2) With the reactor power j
;
less than 754 trio main i steam isolation v'alves
' individually and verify ; cicsure tim c. At least once per week the !
l main steam line pcwcr-j operated isolation valves
;
shall be exercised by par-l* tial closure and subsequent reopenin : I d. At least once per operating cycle the operability of
*
the reacto'r coolant sys te= instrument line ficw che e valves shall be verifie valve In the event any isolation , 2. Whenever listed in Tablean isolation 3.7.1 is inoper- ' least , valve specif 2ed in Table ab le , the positien of at / 3. 7.1 be come.s inope rab le , one other valve in e ach line l reactor power operation may having an inoperable valve shall j continue provided at le as t g be recorded dail One valve in e a ch line having ; an incperarle valve shall be ! g ' in the : mode correspending to
:
.
the is ol ate d condi tion .
- c. 7 -
l P. LAPS
. _
LIMITING CONDITIONS FOR OPERATION i GUkVEILLANCE REQUIREMEIWS , I e If Specification 3.7. I
. and 3. 7 D.2 cannot be sact , .
an orderly shutdown shall i be initiated. The reactor !
.shall be in the/ Cold shutdown !
': condition within 24 hours unless Specift'ca91on 3.7. or 3.7.D.2 can b& rac ,
..
!!
l l ! l l l . l
. --173-l AM 47/47 O c t o l.c r 10, 197;;
_ _ . . ,
-_____ __ . __ -
gh - e
. - - *
**
I ,. . N' ,
'
TADLE 3. PR RY CONTAINMENT ISOLATION VAINES
%, Number of Pc 4cr- Maximum Action on
'
Operated Valves Operating Normal Initiating Group vc Identification Inboard Outboard Timo (nec.) position Sinnal 3<T<5 0 GC 1 Hain ste ~ line isolation valves
-
4 4
'; '
.
1 Main ste ine drain isolation 1 1 15 C SC
-
valves - Reactor water sample line iso- 1 1 5 C SC
lation valken Main steam sampic line ,1 1 5 C SC
3 Drywell pdtge inlet isolation 2 5 C SC
"*'
valves l Y Suppression chamber purge inlet 2 5 C SC
;l 3 i
isolation 2)yalves
'
Nitrogen purge isolation valve 1 5 C SC *
10 C SC 3 Nitrogenihakeup isolation valve 1
.y . .
.
SC
Drywell main exhauct isolation 2 5 C
valves , 2 5 C SC 3 Drywell exhaust valve bypass * isolation valves 2 5 C SC 3 Suppression chamber main -
-
exhaust icolation valves 5; 2 5 C SC
* 3 Suppression chamber exhaust ; valve bypass isolation valves 0 .
l . _ . _ _ _ _ _ - _ _ _ _
__ . . _ . .. _ - -- --- TAbl.E 3.7.1 (Coot'd.)
P H I H AltY CollT A i rlH El4T I S ul. A T i ull V A I.V E S 2f < to - ---- . _ . . .
=
g . . _ _ _ _ . Action on cu Number of Power Haximum g Operated Valves Operating Normal Initiating Time (sec.) Position Signal _, 6 Croup Valve Identification fiihoa rd Outboard
~ - - -
._ _
k*
,
NA Feedwater check valves 2* 26 NA O Process 4 18 NA C SC
-
3 Radiosctive gav sample isolation
[ valves s li 1 5 0 CC M 3 Instrument nitrogen compressor suction line isolation valves
*
14 NA 0 CC
3 Osygen Analyzer System 18 la NA C Process NA Standby Itquid control system check valves 1 32 C SC RilR S shutdown cooling suction 1 2B isolation valves ' a I 24 C SC c7 kilRS shutdown cooling 3 o* 28 injection isolation valves 30 C SC 2B RilRS Re act o r .Ves s el fle ad Spr ay 1 1 isolation valves 2 30 C SC 2C Feedwater F l u s ti Valves I I 20 0 CC
! l 4 HPCIS ateam line isolation ,
valves
*
1 15 0 CC
$ RdlCS steau i 1 es e iholation valves 30 0 GC .
kcactor watet c l e a nu p s y s t e I 1 2A i s o l .i t t o n v a 1 v e I I 20 0 G I
-
2A Reactor water t-leanup syste l j l return i s o l .i t l u n valve , i m
* . _ . * v .i l v e s u s. t si . .. .. . o p e r a t e .t . '
r e.s u l r e.1 by !it: :CG U$78 I t ese , I: t: c.,t e . . . . . . . .. . . ,. l e t t o :, .. ! t is .: a .sti..n
-- . . _ - -. .
_ _ _ _ _ . _____ . . . - - . . . . .. . - - . _ . - - - . -_ -- - _
. . ..
{
~
. .
-- - - -
.- ,
:s e
g TABLE 3. (Cont'd.) ~- i no PRIMARY CONTAINMENT ISOLATION VALVES .
- .
4 4
N Number of Power Maximum Action on i Operated valves ' Operating Normal Initiating
' $ .
Signal Group Valve Identification Inboard , Outboard Time (sec.) Position
]
Drywell equipment drain dis- 2 5 O GC - l 2D charge isolation valves : 2 5 O GC
!
2D Drywell floor drain discharge isolation valves l i 5 NA C SC .o 2D Traveling in-core probe to i IIPCI steam line drains 2 NA O GC $ alA m i . so , 2 NA O GC i SA RcIC uteam line drains , HCIC condenuate pump drain 2 NA O GC ! SA 111'C1 condensate pump drain 2 NA C SC 8s A Torun water filter tuimps 2 NA O GC 2D suction isolation valves
1 15 O GC asu lit'cI Turbine Exhaust vacuum lireaker Isolation Valve
j
'
15 O GC SD 14CIC Turb ne Exhaust Vacuum 1 breaker Isolation Valve O GC : 1 .g 11:C 1 utcam line exhaust drain 2 NA it til'e l steam liste wisrm-up* 1 NA C SC i
* Effective upon completion of installation, approved by Amendment N %
_ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ - - - _ _- __ _ _ - - _ -- - . _ _ . - -
. __ _ . __ - _- -
.
.
.
.
.
TAnLE 3.7.1 (Cont'd) . kk
*
PI11 MARY COtlTAINMEt1T ISOLATIOt! VALVES S .5 $ . < @g _ No. of Power Operated Valves Maximum Operating Normal Action on Initiating
$f Group Valve Identi fication Inboard Outboard Time (sec.) o Positi'n Signal .
o . Scram discharge volume vent 2 2 15 0 GC . HA * ' valves
*
Scram discharge volume drain 1 GC NA
'
-
.
valves
. . * " .
W
'
:
'
.
.
.
.
t
. l
:
.
S
.
- '
- _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ __ __
. . _ _ _ _ _ _ . _ _ _
PBAPS 1
, i NOTES FOR TABLE NO. 3. Key: 0 = Open
C = Closed SC = Stays Closed GC = Goes Closed Note: Isolation groupings are as follows: GROUP 1: The valves in Group 1 are actuated by any one of the following conditiens: Reactor vessel low-low water leve . Main steam line high radiatio . Main steam line high flo Main stehm line space high temperature, i 5 Main steam line low pressure (RUN mode only).
GROUP 2A: The valves in Group 2A are actuated by any one of the following conditions: Reactor vessel low water leve . Reactor water cleanup system heat exchanger discharge high temperatur . ' Reactor water cleanup system suction line brea Standby liquid control system actuatio GROUP 23: The valves in Group 2B are actuated by any one of the following conditions: Reactor vessel low water leve . High drywell pressur . Reactor high pressure of shutdown mod GROUP 2C: The valves in Group 2C are actuated by any one of the following conditions: 1.- Reactor low water leve . High reactor vessel pressure, (600 PSIG)
.
3 High drywell pressur GROUP 2D: The valves in Group 2D are actuated by the following conditions: I High dryvell pressur . Reactor low water leve . I GROUP 3: The valves in Group 3 are actuated by any one of the following conditions: _ 111/115 Oct 2, 1985
'
Amendment :: ;
e
'DIIS PICE LEET BIANK INIENTIONALLY I- !'
l
, >
I { l _. - - . _ - _ _ _ - - _ . -~
~-%-
.
- y%~Q == 5 '. _.,.-;----. . . _ . . --:. .~ .. g. s . .-W,. - TL'T;.,i.wi~d%;k.---
-%. ? m ftT," ;n: n- &.
*
-. .u - m e.~- i..r:;-t %'. %.% . >; n-m-= ~ + = -
. . . . . . .w.1,; s , .. :'%=:; -g%. ? -4-> M8V ,,- Wk.l9r=" .Je '-.w. M .- .- .. . n.;, n q.. .w. .p 7 g ; + m-..: ;; m N,-- -a wT p .
.
- -- . . , . cat eL
,4 .., ..
. -4.--.
M') b.p.4 ..? A S h 5 h
.
M if k, CJ.l k'M," 5 . l ':F " g' h - h, u._, M [ .. ' . , , O' [ t
~-
:
.f : ; &J :; ; J. .:.a ,.:.v
-
.
. ,.: .. . ,ym+ ~ - y; :.
.
. ;.u .n. - . %. .*u.,t,. . ;,y .g y~.a-Q .m
.. .. ;y \ g:.4n . > :. ;iy :y, . . y . . ?n ;- a . .> r . :: .,
.
'L -
.
. . .
l ~.% '-
*: . .Y- . . . . < . ~....-. -
;,i..%.
"
'?:f~.L.,::..y~W9% &) ?. 3h.:.~.~ .v,, .
.g-) ?~M
_
?. .
.
aMdIk% .:']D.7%fA I@flat[( .9 f.U.h::~.).f.?WW?.dQ&3QT&j $ 'N,%.E..: -?.3 : ,.
...;;h.L,
.
' : 2 ' , . ..: Q: ? , I h Y
.7
;. A4.:
. hN-Jug, N;;. "
v . :*$
. .l'.' A.wy . .,.
m -T
.~
. %v.a g;g , @:. e..,
. w .0. . ,
'.pwV.:
~~
-
.g:p.4. .M. ; 2 ".k O MWC 1.?,r.N. N wf ,r.nya
..,..:~
. :. , ,
. -- -~ .. Y. .nU '.'
--e- ;a""
:-
* '. h ' _ l.t^~ - j *,yn ~-. . ,. . - - .
/. . -
'
; . -3 W"'.T ' '.1" ., .5 .
..
.,
; n. ,a ..-%, .. & w:. .. .j"',2.=*W; . ,..,.
w. ,m._,.t.- v- ,f..' , j ,*h .. e . l* *.5&, .x ym&.1,. j'_ [3,:a' Q'w* . p,( ;.r* '
. . .: r ; y . cmp 3 _ . f, n n:, W ~7.cp., . n,
.
r.,, <.. .. :
.
.-; c. .
. -
. ,. . - W: .
; . .<n.:n:n- w .:s.sp . ... wazu
. ggvm :..t. ..c.r,.. .,.... - : = ~. .
.
;.m ,n . . e - .:..4- 3:
.-
n., ::.r .g . . ~ .
,-
. , . , . . . .c. _.. . : ..t . . . <y .qtn . >w n .e - . a:.y . . .
u _,.;n ;. m,.: : ; ,. . . , .. g- ..
- ~
. ,,
N.,
' 'Y. O j. WPRQ
':Q,;,,
'
-
.. 5. u
. ? ' .:c- 7-{:M,*:.':~ $.kh Y:: ;. ) :g..; y';k,h':k ;l':?y .Je 2:.Q.R .x . :. .. . ; .
... .,
"
.
,:qyQ R W L'h .W'T;p
.
.
R. 2 L +:. - ' n;p &. , f .'" - % Q : J L._..'
'iii; Q.. . R. N ; _.; $ 5.V i L[h'@
. . ..
.
...- _ _ p- c.4.a.S.'.y
. . . .
h ?". . - .; 4.'yyy[V.: .
.f.,.:.&m
.
f 5 . W % . Q f.'Q. R. .g Q g. y . g .. . n .
.
- - , . ...
k '. '. v
'[ [ D$ .
,
~'
.Q ] ., ED p; .
.kh . )
.: ,...g- .. : . n~ : .4. - s g -
L . .; 4.8b . .,. ..j e , . ..
.
- [,,. .,;px. Y [% .~ 4.fM :vv . net,3ffi%.,a ~.w
... . - .
.
.. _ .
..
). , . .. .( Mi MM. . . . m-._ T .cr; N F.ff . 1-3 Nfg<r1% N ks.[
' w . + .. ., @ . ;.r . ; . N-~2 hp ?n ~. 3... pJ..:.'p .
%.2.J4.;.i; .m, m 3...,. &
,
c . . . ..w ;
. . . . . . . . . .
....!.. .:;.;: y y:.p.; .,
. . -S-g .. . m... y ,._g , , , .s...:- W,.,.g. ..q.s; . . ~ ?:.1 .
..sc :: :- .g-. -yn y~ . .
- .
.:. .. - - .. - , s
..a-.~
.
.. :
.- . :. t:;+. s. . . - ..
., nx. - -.
-
. . . .; ::, .: -
<.r<:
. ,
.
.. . .u
-
m .g p
- 3 ._ , ~ .4, p. .'c.. QQ. .
. . :.r. ; . .
-
. v m; . v z,..o.. _M ];:! :.f -*Qp,.; .. l&:m.,i g.ci f..,r.+.,~ ;: .
^-
e.> A. y; y, Q)s;: -
. -
- % . ,gg -g,'. . , p:lam .,Q ,
- ' .
. . .
.#1 .
.: y w 3,w - . . . . . , . ~
. ;-.. ., .c ,
-
. . . m .e
~: . .. y. L < ; ; \ ; 4
. , .
. J:f-@gryr.. g . 3, . ny
.
'l . $, , ; pd5 . . ; ' , ..;. ;h.b: ,. : .::_ y!. ; .~ .. % .: ).
.
% : . . Q.- -. r. t . . _, . '.f.h ; ;.:. < y pl-p4;.,f.y R ;[;m .Q
: -
;. ;
:f.W'u,. T &.a c._1},. :. + %.<*.G 96% ; :.: .'.y;-
..
'
;7
.y. g- . p:\. ;. ;;:aw:.n;,
p . - :i ; - n - L. " : -* . - g ;; ; ; g~:. .
. . . .
;, . c, - . . ~ ...
-
-j'j. u . . ;2'M.; } $ freM;T.Ig% ...g:p .
._
. . : .;1
~
. . . . . t. . . % y s. y .. .m_ .~_ .J , ..
.;...... .g.g.g.{i. ;. gs ;g; _.y,, .;;.}t .
y g, (x
.. r.g . ..,
. ,%,. yW : . . .. Q , ' " .Q. .W-..l.- ~._.M...,. ...3.n.; '
.<. ...
'
. :.. s.:. , .. ~ .. d:. . o; :,... : Y. y^^4. ,%.. . k.W:,.7. . h,'.i?f, , i ~
. p
.g j & l..} .'
'l'
~
;;( . . ' . '. . G .l:
f?Q
,. .: .
.
. .. .
~
g'-j t
;
'flW['
- .
.,
a
. : ; . , . .
._ -
~
.
. . , - .
. --:
. , ,. e A.v.: -. , , . . . . .
:. : c *- .n *
- .- p -.. :4 , m . ~. @.,s. %j % .
.. .
.
c
. .
n . g tm'.t s,; ,+.;
-
.k,}.. . .. }:g _ .'.=. .^;. Q ^ ? ~df j .:, - - yhi.&'!.. i ,,l A Q&,.h...?. , .,l.V.:;%j,.j.:.5*p'Qhf;h...hg?'W.& :
. . .'
:.
.,
. :. ., ., .s . w ,, s.t :..s.. . ,n
.
.
.
-
. .. .. r;...c . ,. . . , i . ..,. . .
..
.m6
, fw
:.
.::y.t sy &.. Jw.hn, .;.x&; .. g. r. .;.\:.. ";h &f. =,. :.hth
.
'
.~. : - ; .).; ;. ... .7.f: , y .:. . .
; : .
4 Y,hi - .: A ;-; ,
%..;8,p.ge p. p #:m3 .
. ,
. ,
. , . ;.,.
. . . 4 _. ..
,. . . . , , . . ,
g . . .. . ; .
[.". [E ," Y h d h .:. 3 ' . .
'
.
*
. , '.k.k. :. .' 5 .h'. /
S
- .##,:,3g 3 ,.[. e -. #.> m. . ...pM.,n, %, .c* o . 4 . .A. n cM J,i - Q X. ~ . l .'?c::.?. ; 7... - g:O., ;.(f . . c;r,u -a .. J. . .. :>;i./ ,4,% . . . i ,'f. 4.= %. ; 'E
'
'.'.
'
.)
-,. , < . a : .c;e
. .~ a., . s ~ ~.r x
..v
. . a -
ume .,.. 4 - .
.m.e,. . R. ,.f ./ , y,
.; p' gy.;; v ..q. . .. +
. . g+. u,.
.
. ,'...n.g;<,.. .. ry . ;p.J9;. ,. . : ;.- - :.....y a (
e &, u %. :
..
. . x x ,r.:,; y; x a;.,.;i .
< ..s
-
e 4 ..
-
p m, .
..
.i;#4; . . 9; 2
.
.;; ;, .. . , .p..:. .. ,.r. .m.;a
.
.. . .
.. .g
.. a . . ., , y p ,:+ .a
.
, -
,
, :, ..
-
. ~.
.
+ &,,- :.; 4,. y.- .vy: ..y ':,6~ r .. c .- . . . - r ~ '. .l lb *. .... .l..x.r.',>;~. ,;;*;.,."i., . 1: r:< _. l : :; ' :. My. ; - e.- e &n,
-
.
.- -
. ;.% ;'..@s.f:$ y .. :*.,,:%% Q ; $~Q..:,.iq"J - . . fr.& '
.
.
,
c
% ;,2
~ *
,..;
f.'. % . . ' . . n M :- y
. . ~. . . ,g, , . .v : : . _ ..,
,.c ' ...- ..
_
.. j . . . , - - y c . . , e; .. , : , .
* ; *.. , .
y ; . .n . ,;;; . :.r ; :. . - ' .,....;:..
; '. ;
'
:;.
. [:'6m .. V,
'y, ... .y, ; ;; . i, gpy;s s . . . .' . . . . . :~ . '.y,: -. . . . -
.
. .: -
- i
. '.[ '. ,.
.
. . .
'q _.,., ,-' _
.
.( s;;;.
.,
;;~4
.
. .
5%L
,
,g,[
.
. . . .
- , Q .
y
..
,;'.,.;..y '.:._;_y,;:.... ,;G,.'
- -
t:? "g yH;. :. . ;: :
: A ,, :, 5 % .; ;
;..y..y .n-_
,
.&
_ .. ;4.g - -q' ty - .
. . ..g
. .y :< .
.
'*j.*'3
.:+ ._ ._ ;v . . ,. ., ; * s . ..;
-
;; -
_
; . ;. , . _ c _. _ _+.
. ..:.. . _
.. . - - -
n
. L. :. .
.
.
am
. .
,
y .. ....: -- v : . ,. .
:
.
-
_ .- .s . s,
'
-y[.' :.: ' ,s6. - - . *; )'. : .44%. 3 ^:Ji,; _. .;'f .. <3 l . ;g> . ; f,
*=[ . L; .
. .,. ~. ; ;;
*
:
...
.- . ;... ,+ . ; , ,.
. :
. _,[ ..
-
.
.l .
:.
.
u' ..
. .. . .
'.}: :. ~.;.,.., ;. . ,
_
. .
-
; . [ --{4 ,.f ' . , -f. .. ' l :, * _ _;4,,. .. . ~ , . 2 * .
_
, y. x * + t -3 _ - e_s....,e g ;; ;. 3.,.,- . . . .;;;.;
.s .' . ' n .- . & .? r:
_. ;
. . __ q,_3 .y , :.. .e:; _ .nv.j _- .; _ . y A. _ o. . ;+ .
_
-
.,
e ,.. ;i .j,, ,: :: 'q. @ ?).' t :;.. .HM:. c: - ::l ~ : . ; .h .:\ '
. .. .
.t .!
.. :
.n ...~ s
.a s. . :.
. 's
. . . . ..
s *l *, . N. . -. . , . . , . ' ..
.,.-W . .* .
y ,
} %. 'l
. ,
.
p a' :' L .:4: 2 _ , .. O
. . . . . '
.\
- .;,.
.
.. :..;;.. , q . . : ;p .._4p,e
'.. %
.
4,._'.
,
.: , '
,,. :,,,.3- ,. ' .;
- -
V-
..,
.Qjs:n *M",,. $?I >$$Q'.Ql L:l< cl ~ - c l[.K l. 2:l.' I ?. ;;..Q: A N: .&, h
.
[ 'l -
e,5 *p _a f' '$1 [ * =-. -Y _
. i *. E
'
N .l -'
.
'*- .1 '
f
.
**
.
;
.g,b
..
< ., - - ' . * ~. EI* - $ ;
;f y .grggr --g
-
' j. y, .,
,
;g. . g k .K, ' *;,; l* . . .i-f ' ,. . - > ~ . - Q' .? ], c Z c -4.N-
-
r.*,.
. . any. . :,,, .
D'*_
.,g x: 't -
.e ' s ", . w ,>. # , ,. ._' ,h.as ,.- " ' ' . . . ' , ' , ' .- '
.a O^
.W w s. M- . '.
t -
<
M, .,; y:
.. . i, . j 7 .rg' c '. , ...A :.
." t fe .,k >. '. , %j ' ^ 4.Qv;). '"' *c , .
.
..
, : ' ., u r?. %ws---^^a' . O- r 4 *5 '.g ,
'
; , hs ,., , ; : f.: # :: ..v..,. ..,. . , . .
* < %: : .. y
. ' . :.~ ci. ,.:w- 5 . j. . ,,. ,
. 7#
.* 4*f ..
'l
-
'4'
-
L..lr,..'
* . .L :- =p= .- . , n .- . . ;. ^-- W. .: W. . . ~; :t. :.: . ~,w.,
.
%. . .. #. ;., . (;
, .. t .. : .
-
ao
?
p. , n
.
, 8L , m:; . * g , -- . - .
..
-
-.9 . % ,. q; a
~ y:p;;:.1,,,, s.,, .,
. - + v .. .c; - . . - a. ,, ' ,
, . . . ,
" -* ~. _"- -Y **"*"M{*m; . p -- --: __ l f .ng . r . '. .c
.
_
'
. . 3
.
-
. . , a
,gg;.
.
*.
, ,. r- -f.n, '_ g = [- ~y
- - '
. i . 1, . . , . , . . . < ,- - . , , . . ,' .. -. .', , . _ . .
..; > & u f * ; .. ; , g gy s +
. w.x* m . . . . . . , , - . x- _ .
.
__ 3 .
;,
_
., ~.
,
'gd ~.N,'*' -N , /a#v
' '" '
, , ,' '
l, ,b f.'..,'
'
[ ' ,,4 . + - f" / ,h g O
.[ l* . /k' .)., O %8 ,,.q,- _
'*' 'e .
}'. -' . *+,,**k.'
'
. ' ' s '*I S *s . . '
-
<z ~. u .. . .
. - . , . . - - - - - - . . - . -
i= . e . -- n .: i_ . ;mv= m %. -- he' * ^ Ms,.W. - - -
.-
P-e-T
.
_
,a..., .. -
3 'c.- a xd.-m:?- '.. .-."*-j v M.!r = .dri- s. g.m ~: ., -
--hT c_m.p.-w :._m-y .."Jmrs - 2*rgWW: n :wr-
% - C _ :%:::
-
. ,w
:
.wiressoas-W.*r T;','*f*C'M- Mm
.. .
';.9' :- - e-4e' *"" nj , .
g 4-c n.1d.M.- *v - Pr 1. ,g.,; 5 2 y ; ?, [ g " M ;y&=.& . ; - J-4~:% .*-24 . r. S'" n V
.
y;WW . -":. %y, g.%y,& M .m:*;f .
='Try
~
- ~ ;. ' w .: ; %
. '. ; ' ..c - c.: 7 ?up ., ;- ,,- gypgp g j. .. .
,-W fy -; f Me cv :La.la,=,w,s y'?- 7... '
..
_ .,' .. , - s ,- - '. n _ . - , . t .1 - n,.. . .v5 >- ' . t '
- .* ' ' ' ;. -. . . . . +,iL.o.Q .^. ' . ,v,.w:,.3't*
f- e a.,--...g 3 . I a ?. : ' -;f1 . - - .:. - e -y g. _ ,..m =.%..~.; -
.;
; .?: p , m e -.-- ..
n - . . . . ' 'w ..:
. . - .
_.e-
[.7 y ., "
.. Q i;n y .2 , c _ #, k #yn *M^ Q d
'
g,.. .$e%' /
,. ( i.$gy...
.-
.
F , , * .. ,W - W-. .. : S.:u.~.1.%--- ; h.ibi.'".y _.d, , . M, i;" ; t i2.;r . - . -gM *w
, .
.
. lMt- .v
..
-
-
- s . .. ;,.:- ;.:-WJ kjl~?y. %gNk .s. s. . .2-- _
, .. . . .
.. .
.
? . 45 ' Q . .W'O .) , , Y.$D .:'.l *A &k.. ..$.N' "I ; ' *?.f'-M %.l'. ,' . l . -{:% .
.
-4
.MA w;_ .:: ':-
.-
' i%m , ? ,5 . t '
k.'~. , e.(' ; . , 2 u ':,, t . - . . . % ;,
. . L %',.&_1 .$ w.w:g%y % .798%;be:,a~ . . . ..
&y***., .t. .i.K,'i
.
*
-
: .. ... , .. f..*'..* . l;- r.r ..+ 7~ : .~ z s.? _ ' \~L l ,
:.
'
;
-
:: _,,
- ;
, y .
rh .
-Q,:. -j,}+.f .
*
e S
.31.%r [ . . ?; ; i '" * . . . - l f_* ~., '
.!.....-~; )?}i.}}f. fl l : y.* .; ;' . "., .se - . < <,-.
. y r ......a':...
% g%.r.hagy* . . ....=.
.
~.l;. ..
.
. ., . .. ,. ..
_
.. .
. .+. L .? .y Y t_ . f i. -:1... - . -
-.
.
, ; -- x ? , ;
< r .q;; - % a Q y, - _
.;
"
'
. I -
.
~
.
. .
e . - . avan e* c
,
= - . .. w n, , . / '. - ,'... '. v* . . 444. M Y*.
*' ~
.t ', N - y c a
%. .M.=
.
' v
.. ..
- 4 . - ~,7 - _
-+
T' W = .4'v g !'. "[..,'1yf f.(! p C 2 h .'.)k;~'h' p' ' N [ d y y ~ , h l,e !').9['. ? f[ 's
'
' "
[
*
"
. .. 'i,. Q.', , * e vi '. ,
*
. , jeg g f ' ,,,
'
n -*7 N, ,
'
y'
. . f. e=.s . -7.* / . .. . A ,.t : , I * . 'Y -
' * ' " *
), ...#.- : .
8 "**f
. .:p . *
-..~-r,r-'., t' $
%*. .a
' ' ' pe,'3 :
,,.,
P, -
.. , k. k., . $ . y ';. ~.N' g ^ '[ [h '. b* [ . . .i #yabg ' ' %. '
p .3:, .. . n w .
.M y ^
-
-
- . . . = .,,, - . /
. . . L:. .= ;h. ' ,.
**- _g,
=
:=~sm.- .,,l,;.
f ;,94,gr ?.7 7 f . *'. :. f :. . ;.n..;... - ~ 4 - . };' w-
-
_
- ';
_- - . ;? -
. ' mm_ <g:'. '
_
; .. . ~- -
w a r , : --a . . , , - : mem6 jr g,e,
- -
.
-
. ' . ~'j g~_ .,, -[. a ..%l ,,.~ #
.
* '
k .~* _,,,,_b.,
.
, . ,
*[. .h., y ., .
.". e.... ,,,, . _ . . .
. - -
,.
.. .9 eu
.
.1...-.,,.p-,, ,
,
44. .,. , , [
- t' - J- ~n.- ' , , , . . 'm-e.n" . o. ~
e- M*8 _' - - .. _ . - .._,.'.'8
-
*[ D' .
.
.
g ;,
*
* , ,.
'
. j.. ' fger ,, , l
-
..'.[.- T. - . .,
ff ;,
'
*
.,.e ,y,.
'
,
P
.- M.,Lj.,Y.g.h-pjll(, .j j';), * &.. j _ - ,,
).
' E?,, , .. ',,.
,
{
y p... s~-
.l ~ '. 3 . . f.fYB
,..
V ye
~:
-- .
. . .
" "? U
.
\
(
.' q
*
.
. * * r a 9 .
=
...... 4' f * * Af -[ '
"*
^ - *, '. *.[. ).' .6j Y'p..'_ ,h
.* * - ., , -
g / l "l: ** '-- [ * 4 .. - lN y # !- ,: * .
*
e , , .
,
,., l '
'" .*'*. ' ' f: * ' , $f ,
[ ..,th. _ [ n +: L. 3 f .9 N. , l, 2u ..[ Q _ sL ';;,>.' ._ j .L
'
, u g _. ,
.....,q ' .]~y .t -*w' . ;y-
':(.t ;hf h.$::.';
. _e i ..
.
i : y,y:..? 3 - . .: t ^... ;y, . . . - 3- g .. ,,
.
: .:
,,
;,,....,,,...,.;t .s s , . '.
..
...,.,,.m
. . . . . . ,)
u,
-- as yes,.
4 a .. f. 2
-
; y. .j ,.
-
. . _
p g. g ff Q 7 . q
~ -.
3, . , 3;R;., .
..... .- : " ,m;.
-
.4 -
ca,.;n a.p. W :-.,p;.. . , y .y .. 4 ;~ >~, w y.... ..:w y : r,
. .
-. a g.y ..-:r.. w,.s
, . .
A: .
-
y
.u ,...,..n .- !
. - .;. - -
. . . , . . . .
-
.. ,
i C . M,s,. ,7 ~.
.
.
.
.
.
QlMW - TF . ,- jg] 1 { k4'.ge .:n . g ?.p$. .
; . :. :. .
:g , a , . fsj/
.
g $%Vfk & R 4- b
-[ '.
.
. . -
- 5 ~
+:,y ..wv..' ,. > j' 2.hOff T .D 9 -* ..
x .. P :. , .,:' ;u.- x ;;.,i , Y:17,".y[. *m.qm4[.._ V_ffNO ... 6.n.%
, ..
.
e
. . .
m - :. . .,a
-- <.
i-mr :-~c . ,.- ,r:w . - n~ _
- , - .. - - - . ,. ..;
v- m
,
w . : . .. wm:&e- ,
'
. . ;. w . > ,
. v
,
- - g&. Q ,-.,. ..K. '? Pr , . A - .
.
.
. ..o -
.. - + .we.:. . - ~. r. M.&
-
.4 & n., .- :3 .v . A ,p. A .. :. M n.- . .
= _s .s
-
, .
, N, v, _=
-
{ ?
*
v. h
. #
. k &Q $_.hhf.;f.{ f.: .h.f. Yh .
o n 3 ." : s %
:
. 5 * {N hf. . ~ >
* . 't . '- : !*
.l,f * f Q Y
. .
.
v:.n $ ~ w w; m . ;j s~w %..;: ):~..meF :::c; <v - % w '. M M.:.i.4 ,p ;:k). y : f p'W ; =
.m194
.
c y> . i.= a: w -
..
1 ., 7. - y p.y, .. y4.,y ... c. z. o . y.... .> . .. .
+
. < y9~_ .<.p ~ -. ,.. .
. r ,
:>
.
-
:f. g;!fe. . ::. . .r. . . ;y , A; .. . . :y..
. . . m
, .gt... g.y.z .; ...?. . .
.
;,5p. -, n- e
.
.'.
- - . ', > .' a%c '). . -- _. <
- .
-
y
.. .. . . .. , .
_
,
w > ..
,
y, . ,m . + ; : ;: _-;. 3 :. x..: , ~ , . . ,c., -
.
. ... ., ,. p p-
; ;~.
,n,....e.....r.3.,,
eg,.. ;, . ye . . -. . , . . . n. ...?, .~4 , .., ',:g s., ~_
,
.
. . . l.,
'
,
, ...
.
,g;Qt: s gT .. n y.~Q.... _;. . '
:
p. . . % *
-
'
' - -
' .. . p-'ec -
-
p>.-V.* ~ [~ 3 ' :. ;. %nw ' . <g
,
:.e
_ ..' f <, . 4.py.;- p[ y'
.- 'o *
-'
y
.
. . :. ;+
.z. ;
.-
-
.
L
:.. g g }y 9
.
4 Q .s , g f.;;.~::. o _ . Q;3 ng .:3g ~.a ?.:{' , y
: .: .Q.y.gp.;g,%.:;-} Q:..%. _;
_
, . ,
) y_% . ._ . ,
g i-m,,$. . + 4;
. . . ;_ ~3 .
3 9 . .,, . 3 ,y. . .. o.. p :y ;;.+ f z .* y , ; y .p . ..s . ,.qs, rp: .'4 ,
. .... _ .
R,;y..:. m. , . x.-;-c&- . .. ,_~
- . . . . . -
_ . ,c ..,. g.
x . s
- ..
. .
.
. . c . .. , r .. %: * , . ,
-
. y ,
.y
. ~ ... 4 . e .~ gyy
= m -" . . . .,. ..e s, .
.
,n ..
a
' y .. . . y, ,
g . ~ .*.. ,. -
.
*
., 4l .
.
.
;;y . v,3 :. . 1.% -a. - ' gy/T, .m;
..y',A. ..F- .. .Y 5 ' t;T.?
wm R F
~'e,,, % l . %. . "!.", .' . . , . . .
--
* **
* j'. . ' L<
g '~. '. . "l v.&? - .~ '. :y n W. 4 :h7'l
*
g -
. ,.g ' & ,f ..'. 4~ 9
.
;
,w;g
. .
a [ l-. %.~.-c..: v W - .
- C.,...,?.. L -
& - :
w- . .r W
.
,,
,x. * -
.i....
. . . .. -
.c .- .
. . . - . - - -
.., . . . - .
..; m . .
' '
+
. . -
. :. l. :Roactor':Voss.bli.las y . s. w:terl level. . ww
- .. -e4@ . -
. i.w.' d.$',M
.Y d.,iX;: ..y
:13. y g p... .. .-?,,t.gf&m .
, c*: .tg ;- r , *;',. /b C ,-
,
:c -
_ 2, .High, drywell prqs sura.3 g .,w sl . .y.# t -. h-
.
.
~.g ...1 . . .. .
. . . .,
, . . .
;
.'- Reactor,buildling . ventilation enhavst .hi .h radiation. '
'
; :.;. . =y.q .v;.5
.
. '
; - .
. .- ,
,
.
-
'
4.. Refuel floor ventilatten -
*-
exhaust.high radiatio . 72. -; .'- .
- GROUP 4
- The valves in Group 4 irt, actuated by any one of the foll'ow-ing conditions > 9. c
'
. . .
~
.- ... HPCI steam line high flow." .
.
. ... . . . .
2. . HPC I steam .line space'high tesperaturel,
' -
- -
.
-
2 . , . 3 HPCI steam line low prossure..-(except for EPCI steen line exhaust .
.
.
. . . . drain valve AO.52147 actuated by either of the ) -
. . ,
GROUP 4A .The'valvos' in Group 44 are following conditions:
.' ~
-
,
,
- .
,s ,
.
_ Reactor -vssnel . low-law water level. ,
'
- - .1, ,
.. ._.'
- .. . , . .. .- .
. .. .. . . ,; ~' -
Lj- f2. Nigh' dry'well . press'u rd. 7p.,I . . .
,
,3 ;.
le
.
,.
.
- _... .. .
..
..s
. , . , -
.. .,
,.
._
.. .
. .
.,..,n. . - ..
'
GROUP ha '
.The. valve'-in Group .48 Js actuatedMon both.of- the follow U- '
1 ., .f ing 'condi t t on's tare 'pr'e sents ' .- ~ 7. I J
-T:P'?,Ib[. M?f *
l*
.
' High drywell pressur . . . ; .. .. . . . .
? yhM: 3 . T45-
.
.i/ . ..
, . . .
, .,: .. HPCI steam line. low prosaurs. . 3
,
~
! ' GROUP 5 : The.volvos in Group 5 are actuated by any one of the follow- -
*e -
ing conditionsa.:-..- -
,
y i . .
.
- .. . .
l RCIC . steam' line,high flo '
-
.
.
j 2. . RCIC steam line space high tesperatur .
-
,e
.. .c .
.
.
-
.
..
,
. .- 3.}.:-RCIC stesa 'line low.-pressure *. .v, .
,, .
! GR'our SA:' ~ The valves in Group SA are' actuated by the following
.
conditions - '
- .
'
/
j: . J 1. ' Re ac tor ves se ! ' lowilow water -' lev l .k. ;. *~ r ' l ,; . _
.
.-
. GROUP 58s- The' valve in Group 5' 8 is actuated when both of the following'
'
:. I ii
.
condi tiens ere pres.ents . ; . @
. . .
-
+ .%i-,' , J. - - ..
. l
. ,
...- -
?- .-
! - 1.')itgh drywell pressure. ...
< . -
l lr
.
!
=.'9 +' ' 4 2. RCIC steam line : low ! pressur '
' .
. -
., * * l
.
; <;. . . ,
-
,. 1 - ( . . I ' *
<
.
-183-44 - -
,. -
.
- ? Amendment me. 3, 37 .
-- -
. .;.
3/2ust
,
- }.
-
.
f, :
.
I __ - - _ . _ , . _ _ _ _ _ . _ - - . _ - . _ . . _ _ _ _ . . _ . . _ . _ . _ - - . _ - . - .
.__ __ - ., m
*
t . _ l PBAPS ,
- !
,,
'
. TABLE 3$7.2"..
TESTABLE PENEFRATICBS WITH DOUBLE 0-RINGS SEALS ~ .
' ' * .>
Pen N Notes
*
Pen N Noten i
'
.
N-1 Equipen (1)(2)(k)..E-3NA TIP System -(1) (2) (4) Access Hatch (6) through '(6)
#
N-2 Equipment (1) (4) (7) Access and (8) (1) (2) (4)
' .
N-200A&B Suppression Personnel Lock Chamber Access (6) , ,
. Hatch N-4 Drywell Head (1)'(2) (4)
Access Hatch (6) N-213A&B Construction (1) (2) (4)
. ' Drain (6)
N-6 CRD Removal (1) (2) (k) Hatch (6) , TABLE 3.7.3' TESTABLE PENETRATIONS WITH TESTABLE ELIMS
.
Pen N , Notes Pen N Notes N-7A Primary (1) (2) (k) N-13A RER Pump (1) (2) (k) Steam 11ne "A" (6) Discharge . (6) N-7B Primary (1) (2) (4) .:N-13B 'RHR Pump (1) (2) (.k)
'
Steamline "B"
" (6) Discharge (6)
N-7C Primary (1) (2) (k) N-14 Reactor Water (1) (2) (4) Steamline "C" (6) Cleanup Line -
(6) : . .
N-7D Primary (1) (2) (4) N-1 Core Spray- (1) (2) (4) , Steamline "D" ,
(6) -
-
,3 um P Discharge. .(6) ,
N-9A Feedwater (1) (2) (k) .N-16B ^ Core Spray (1) (2) (4) Line"A" (6) Pump Discharge (6) , N-9B Feedwater (1) (2) (4) . ' N-17 RPV Head. Spray (1) (2) (4) * Line"B" (6) ,
(6) ,
N-11 Steam Line to (1) (2) (h) N-201A Suppression (1)'(2) (4) *
*EPCI Turbine (6) through Chamber to (6)
N-201H; Drywell Vent N-12 RHRS Shutdown (1) (2) (h) Line * Pump Supply (6)
* " W* - - . . *
g /%
(,
c .. Amendment No. 16 APRIL .1,1976 -10k-
.
, . , , . . . . . . . . . . .. . , ,
- . ,
, . . . , ..-.... .-._. ,. _... _ _ _ _ _ _ ,- ,
uummmessimumuun w -m ,. anm v.w ,we - mem,wn me _ v,nw %.e w+as, w + .r ? m ~ .w+ - - *
-ern n -
m ; . =p . 6. ; r w ~ bn . . % q.y:m_mw y '- C,*%.,., *& g LY.3'n*,+- 43 s-.iX, ikni.&.Wy e i.y %y ;. *%. .,. ~, ; s? P+ n,-.A>c:4Q
-
- . --
N '.;;. ,w- d. .$W ~ . p n ...'", r
-
' .
. . . . ?
L f - ,- i Q..,4j .,
'
'
<
. -f
-
fjp j h ,-.t .
. z .a m :
..,
.,, w - : s - ;m . :
i, 4 '. - -
.:..
.-.
*
. .- . c-- : , ,.y 3 .3 , w
.
.u Q.O j ,' , ,g ' _ '. [.. ,s# .%Ql , * ~ c ylyl.. p '
... .
. + . . . . . _
..
'.
'
#'*
7 * )y\ .' ( . [ % ,j ' % . } " '. 6 ... ,
*
.
]] % f.rx, 5 ;' r.- . . . , - .l l_ O,? : %.f. '; * - k[J. .l:jp . ig
.
9g; -.m s.,
.
4 - - , ~ . . . , ' , , , . . . .t - - n ,. y _y- ; .,. ; v. ,s,,,. 7,l",h. le.f- l ' , ' .-
, ,
...- . ..4 .
. * .,, m. .c 7 . .
i....- n .,p s...
- w, .: 7 . , . ,
. + + ,; ,, s
..._sf ,- *
, -
- .y i.. g,.s
.
. , ,. .
- < . ,,-
s ; ,,,.
.
*- . -
.. :. -, = . . . u :, . .,.. . ,
-. .A.T.,Q . 4. y. w r, )/. . d, T '. .. . - . : .
...,.u.'
<
,-- ,
-
w, 6
.n.,, v.i . : 3 -
+c 5
.>
.
; . . w
_ -, c* , , _ p .., ,..x*- y -
. . . .
. . ,
'
-e g .- ,n'. e
..
.
- . .;
'
<
% .t as *
, ,; ,
. - , , , , g, *. , '.. ',- w ,. .,4 ,
.* ,8-
*' ;
~.. -F;- -- a ..
..
,
#
k
.
. . 3 ..4
-
..
m . ,a
,.
, .. .,. yy . ,- * ,. ....; ,3j, ,; * ,
. '. '
7 Q
'
t ., . - . 1,- , - ., .. .. u ,- *. - .. . ? A
. .. .
.. wc - . s
..i_'*;- , .'n + . . q*Nf - . <",in& ..'..>..
-
, , ' . .. ; - ..:. , ,"[ ..q
'_y ., *. ' -
-
9,<V!
, . .
M, :nj'Q q x , ,. . - . . . . g . , >: . 4m..,.
- : -:
, . .. s : ,
, ;, : .; , . 4 .-
?.[., . .:_g- .*.,y y, n, -; ,n+
.
.
. .
~~.o
.
- + ._ . - .,
; - , '; .' .- . +. s,. *
.
.. , *.
p .. > 7 .s ~. " . ~,- s ' .~... t - , .
..~ n. ;. - .. . ) .,. _ ,- ,n',
. ., , r .n
, . .. ,. . , .= v
,, - ' . , ,
-
. -.
.
. .- . . ...1,, _ . ~ ,
..
+
,V [. . . , ,. ...'.,4< N.S. y- y' l .e ' , '. ,.,; D. ,, . -. t .'.: - .... .(~..[
' "
'. .. . -E .- Y ' .. . ,' .' g EQ-. .<., , j. . " ., ,;O_ . , , .s
-
--
~ -
, ;
. .
_
. .
. . . . . .
.
6. -_ , '
.) .., I.: ?. ,
.Q.., .'Q
:. ;., ,
- '
_ f . g .g ,; }
',
; a . -
' l. . < - *' .L y i *'; '
- ,j. C % , ' '. ..' ' =.} .? sj I *' A . & ,K7 )
, ,
iT., v. - -,. . i..y9 %
.), ^ ' ' -.'. '
-..- .
,
.=.
D %. . ; .W * ".Q : .
+ :2 2 , - ,- . s e K. r . - . %p.;_ Y.' b,.c c.'., A ' 'l . ,,, ., ., .. , ,- - -
7,;- , :
.
,,yl- , - - i
,
[ 44 ~r .** x ;s ,
. , ' . :q . , . ; ,. ,
-.: , ' :.:c -
,b ,' i , . . ,
'
.
.: , .f~..,
-' .'
z;. e x '. r . p - -r.3..--..-;, . y .. - .. ., n.v . _
> :. .: h . _. ;n * -
<,
-
s <
; .~. ..* :3n,,; r%.; .
- .... ..~L : ..~
v . . %s... .1 *
. . % ..
-
. > . . , . .. v - , :- - ;
u .- ,.. . . v
,
: .
..-r _ .. ~ 9 . .
. .. - -- w
.
-. .
y . .(. . 3 ;. - e,? , = ~y ' s 4 .g
, , - , +
9,,..- g ..
.. .
. . . .
My W. ; M,g' . :t y . ,.*-
.
"
n k ?. W +.. _, a * _' i. .l . , J .-".: -~ z .,# '
, *+.
-i
*'
I; * '
'. 4= -L _
*,.
. , . . ,.,.- %.v. , .,.,;,,,. ,n *
.
. 4,
.
,4 3-
, ,
, ,.
, ,-'- g .. * .
v,c .& wcf * , ,.- p a
..,..,,n-.;$'W ;. .s -
...a
., .
-
z,
. .
* T g ..,,.s' >' j-- ':q y 'n' -
u>
[R.%* .' , - p* - i. . , . .; . ; . .. D . .,,.e
. . . .
y -
,..-p-
. '
*C ..g .
. .Y'e ,!*, $ . , ,,I . . + ,
3 . . 2 8 .
-? -T <- E' x
;. i' , . . . -
. , . , ; y U *
*
4 .I $.sai ^ .'.. *, .' = E ,. ~ .
-
. ., k' -
y
. , , . ,
- - ';
-
s s s. % *** ,~t-vh
. .
*s_ . - I*
-
_ .
' '
< . f, i '.. * -
* . , . g . , ,. A . - n
'
:' s, ,V +g
'..,c + , g., .w .J.,
.
..*-. ,. ji ';- ,-
. . ,
,',,* ..
. . ~
'. '%4. .. - 1.,: 3 'y
-
' -
'
y-.r ,(_y u . a .1
-
. ,, - ,
_ .n J ; , ei -
; i ,,x .,,,-.y , , _ 1 ' 'm - t . ' * n , .v .
',,f Le g-: - .g,- , * ,-
-
% y*$* <-
_
. .
_
. ye
,
n v, a _
., *n,, . .- . . , .
. .
y
,
- . ,
. ,
.. ,,i-%$- . ,y i, ., t rT .
-
* s g.2;a; -...a y}, Y"y y; , ~; 3.q,s 4
, *.
,'
, , . * .f f - f .' . % ' .
'
.
$ , ;. <k \ -
I 8, ..g '/ . ~ '-
~
f '
*' **
,M - .1,. e -- .- _.2,, . .. j . 3i g . . . -
-
..f.' y
,
.'
_. , . ,,'. .Vk. 4k: .....T -
, ,
'(? .,>g +:' ' .x -
.'* {~ ! 'j ,, , ',,[
'
*
., , k ;* i .* 3[ \ < dr.f . , b/ [ ", * - +*LP ' . [ d,t . ..] '. '..
'
_
*
n
.. a, .<-m ' p ; 9, . ,s,*
4. '
, .,.g
'
. s
,.j
.. s ,.
: = < c f .e e
,
+)s, &>;
. , +.
* , . . ..-g. g..g g( .,.s .
S*
. . A= . % . - -
-
-
. . . .
i9-'"-.C. ..v a; ~. .. ,.:,,..# .
.,.,.y,,
(
:
.- -
.. , t
., ,,. ;
..,,s..-
,_. , -
+ n. n.w . s'v - +a 4 .e' r
.;
f
- re
.. e
,,h'...,
..
s. ry r <:
.
tu L,
\
. .E
-
,_~ ,
- l {. . Yu .*. .
<h
-
('.. w - . < b... , .- * e -. p p ' 3, ._ I , . # ;
- *. *
%:6. . .t '. ,' t fl
'.* . u. . . , P
*
. <-' .' .? g^ .
<.sy_+%p ,.-~-p g +
~
r' R ' i.- *T., %. , . < .
,
,, .- .' p ., ,
- 'e i # -
'
*
-v o ^':~ 5. i ' E ,
i f, a*M, ' h .. ,'.-
,d lg f- .
*
,
[$,-$ d.{ ab IWH h.$ ,
kg.hI. . ,; y, .; g ,,y
.
:g . V- , * .- , 4
~ . f.h. '; y , Y% L .-
g,3 .- y., ,,
<
,- : , y-:fs_ v n ;.,4
? *
. h - ?. m"* f : i ,;. . .'.' J y. . y ' f . _ , , ; . 9b d. w;. v.. . L. 9%y;.? G[% .
q_ $ %
'
#
, ,
.
. *- , ,
s;* -
% *
. . * *
',
- + 1,3 g ' ., ,.t l- *
,j ,
.g *'*.
- ,
-.W
. . ? * ;% <. 4
, v' , ' ..j, j,- ..j k,.',.,,',, ' ., -~*,."f.,
t - f. -- i
. .Q j .9
+e * ., ' .l
,
, , , _
j y
*, gn ,,'e., as . >, , . , $ ,g . .,
- -
.
,s,
,y,
. . . . .W* . . g ,. 7 . .,.
. -
.,
,
L ,
. ,,h . .-, -. .
:.
,
, .., : . - -- .
+
w.,. ,
. . .- . a 4/ . .. -.<
..,.,. g'm,'
+
.9 *
.. ; .. ' . , , . t--
.
t,; ~, .
,
- - . . ., t, : , .
.
. . 3
;.
,
, . .. .g
-
..-i - . >.'4 .
>-
l s
.'.
m ..s.rs :,e e
+
.Jg y2
-
,
, -
z. . .'~ ; . . g : v. *. ..s .
, , ,. , . .. .,
., .. : . < - r. - . , ,... c . .#. c ,. .
.
%. ~.
. , < . . . ,. . . -.. - " .t . . . . .
* ...
, .
e . . p y .< . k ; \ ;. , ; - e -,- -W,.n/ < > n , . . :y ~ . . .
- , , , . e., t-:
. .
y, +h..9 +. ,. 4, g. , '. ,' ,.- ;,. -
-
.,
, .. ,
R . .>2 ,- +i v
.. ,
... . . . . . . d
..
,
. . - .. a- ~
.. -<
%, . . .'- .
..- . r s
-
% .} % Q .%l,.W, } ]'ng{ ?'\.-l./ g], : . I ; h ',; ._{. f;,.n . ., [ ;I5'_ L .. ] l *;, w
* . c . . ,. f. 9.. l 3 ~d'; g wN' .j T., h
_
= 3;.; ~; i,/ ' ~j. g, , i d. Y .i [ (b
&(:.b(gf[&&fy].l ' ' . . - ) s ..f'.;-
-- Q~ Wjy'lg:- l ,-)?l Q - h . q .'
.
.
. , g i .,
.;:l,. .
'
k l ,yW f.., ; 4 ' , s-
. . ,g - g $ f,. f. t. t ,,, ,, f.' 4; <q. ?., c:' y . p. ., . n.(. . .g q. 7 . . t y ,. 2 1 3
-
i .. .9 w hq n>, J
. ,
o', ~' m < xe ..;.s3. . . .~
.
.P; ?. .. . 4.. < g. .
, . n . .
;
y."'..
,.
;
..
y : .- t. J..a... .
. a vs d .- -' * 3 . t. R. . < - . r x , . . . ; , .. e . * .w , 9
. ,' c.4...,<.w5
..
-
. .y i .@ . c? f,.y , ' Q . , c. , .1 .,e., , Q- ,,. ,. . .
y ;. i
,-,y= - . . .x .. . y.-,7-r +. ..
> , . +. e..,.,. u, -. .. .
- .
. . ap . e, r
-,
.. -.. v
.
y, . . , ,, . , ...n.... . .. -. . ., , . ,c. , .. , e .,, ., .
-y-,s . .. , . +.
. .: ,. . ,
.
;8 i:. . ,.- y.+ . . , . . . . . - . .,g.-
:. u=. . . s, ,, ,.n.o .i , i .. 9. 5. - - ,- , .,f . y s .. .7y
.
.
.
,
<
.
,
.
. , . , . .. . . ,..., , .
+ .
,
.
r,. . a .. . ,
. .- +w .
y .L L C N;- L;
. , . ;
l: .L.2, f ; )_ l,'y. ?P .' e : n r .* ' : . . , : ,1 [:
'
"[;- - W,..-2
- we-
.
. > . , , , - .+ . * . -' <
i -
, . . . , ' .- +.- ,?. .' ..e> *
, ..'..l, .* b P L. .b - .-
}s i.-. . '7 >
l [. h~? ,.-? . l. , , [*.' 's ;,. ,_".. ~; t. .' .'L L~ ', {
, . -
< -
,.
'
..' '"
- - , -1 ;. 3 .
,
O! y,. l Q, i,l4-pj. ,-
.a. .
_,.
:, } 0 . ,
,.... .. .,i,x.-
,
s
- ..
, ,l','%'l.j_+
.
-
p .- . - -
.' . ; .'5:
. - - ,. -'%-
. ., -
', 1 :, i4 \ ,. , .. : .-~. .. ^: . -
-.. ~* ,
. .m . r,m r.-
-
,
m.,. .. .s.4.,-
, . .t . . m > . ., . . .
s.,.. . , . , .e w,,u.-- . .-
,q,D ,c.p.p' , ,
...,,.,n.,._
.
.
... . .
,
... i, y , .<.
-
., .
,
,1 o s. . .
-
., e
. . . . + - .,
.
,
.j . .. " r - ,
..
, /,gc.c, . , .q;. .. . n. - , . , ,, . . ,..
,-
. - . .. ~.
..
.
,s . . . ,, q ,i,.v..-,. _,- y9 ..
.
> > .,
.
-
: * , <
> .-
. ~
e w- .,? * , y ' u
.a .1 y>
; r 4 M.s c . .. . 3 . j. .fj..*
. .
~
.r 5 E. I _.%
~ U < ,7 , - ,, . i . ' .;-., - %! , , -
,>
.
.~.l -
. a s;.. w
- .
. .
. ~
> . .
.,,., 4 . c. g, . . . . ,.
.
..., r
., .. , . , . .. -.
.-
.c -
..
-
;.
.- -c
.~. . ., , . . w a s .
- 2
*y g.' 6.- d . i- >;. .. p ,4 .-
, , # < - ,, g. . . ,k * L=
! %,g.[,a j; }, - - ,., -
h % .. * #,*.--
' ,e - c. ' : .V s ., , . ., .f . ;. ; . ~ .* f;,$ ' ,' , # f
- '
'
, - tl .g Q["p A .':.1' ' ,. . ; >[,q,3.h.G~,',Mg(,. '_ y .. +.h ' ) ' U '^ ; V ,Q- -3, ' . y . R y 9, , .' , > '. c . - . m
-. '._. -i. .: -; ., / 3 :^
o.4 - . ,.. _
. . . .. .
d, y . '?;'
, ,
^ . . s . 4f (-
. . .
, ;.9 f. h 4f b ' :, : , ; .Mw, , . . . W m b * , _ b[ _";.
.**:N" g + . ' e v T
-
, n~ n v
:. p : 1 4 %# Mf"v <p,# ~
y ?d b. ..,M': , ,,,'V24.',0.,
! :. n :. y ' ,a . -4';'& e'
y,
'
c . n a - .- i wn.'.-: /.,.O
>
' , . . a. ? ,-
4.,,.~j j .p ,yg ,'.g' ,; {. ' g [+ p. "[r'g* a - , .,
.
4 k ,?._r, ; . '! *ly { }w.,. gy,. .t.., }.'f.q =*,8 g %w.f.- Aam]nc.,
-
.y3' [.;{:3Q - . .. a .
.a , . . . .
__..g. & _
.. .
... .m,
.
s. ,.. .
. .. ..
. .. .mw , , ._ & . . .
qmJassumnWW4gyg + * ' 4 ~" _
.' '
.+ ' Y; . . - -
.: , , . : * -
f, 7 '. , g
- .. .
?.'.. (^.
...
+ i ' '.
.- 7,
-
..h ,
*-4
.$ ,- ; *A ,
' ' . . . .
rI ,f S .,' \ [ '_[,. ?,' . 'L.>.
. .
5s f.. . . ' .w%
.,.;
b . " .. [ e_. ' '
.
~~
.,,.$) W,_ .
5 ' ;ly . _' fx.R.y y. .f ..[.\. . . . >
. ' .wsRW,M ,a "r
> - g'.R.}g :i-O &
*_[ j:l
~.*M lf p. f} .
-
Y, J T U4'.MTd,.
> --
rw
~ . . .
*
": . . :. ! . - - _ ; _. p .,
;- ' f A ., .; _
q s;.', ; gy ;. g' g - , ;. ~
.
j' .j 9 . .;' _ '. y *; .-
*
7 ". '( f -[[; . ( k ' .;,wa}_...- . ,. , , .. y 3,s,..
. u .... ;. . % .i ; :{- w y: -
,
.-
-k .*-
1. f
.. ; .. - h , ' . -
-c
[, j -' ,h...-, " _4., x2 *
' :4
;. --
,.9 - +
,y ..s . . :q ev- 1,n, _ .tc ;
}}