IR 05000271/1986011
| ML20204J790 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/25/1986 |
| From: | Keller R, Kister H, Lange D, Turner R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20204J784 | List: |
| References | |
| 50-271-86-110L, 50-271-86-11OL, NUDOCS 8608110194 | |
| Download: ML20204J790 (100) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I EXAMINATION REPORT NO. 86-11 (0L)
FACILITY DOCKET NO. 50-271 FACILITY LICENSE NO. DPR-28 LICENSEE:
Vermont Yankee Nuclear Power Corporation RD 5, Box 169 Ferry Road Brattleboro, VT 05301 EXAMINATION DATES:
June 2 - 6, 1986
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///A4tf/7 CHIEF EXAMINER:
R. Turner, Reactor Engineer Date
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REVIEWED BY:
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F0A 7[2MN D. Lange, Re' actor Engineer Date (Lead Examiner)
REVIEWED BY:
If 7[4 /(4 R. Kel'ler, ChieY,~/ Projects Ddte Section, 1C APPROVED BY:
7 I P%
Hafry B.'Kh ter, Chief, Projects Dat4
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Branch No. 1 SUMMARY: Operator licensing examinations were administered to seven Senior Reactor Operator candidates and three Instructor Certification candidates the week of June 2.
All candidates passed the written and oral examinations given that week. The facility expressed the opinion that the test was fair.
All candidates did well with the exception of answers to four questions.
These were questions 5.07, 7.12, 8.06 and 8.10 where the average scores for the group were low, Ogjei g y $$$
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REPORT DETAILS TYPE OF EXAMS: Upgrade (7), Instructor Certificate (3)
EXAM RESULTS:
SR0 IC Pass / Fail Pass / Fail Written Exam 7/0 3/0 Oral Exam 6/0 3/0 OVERALL 7/0 3/0 1.
CHIEF EXAMINER AT SITE:
R. L. Turner /D. J. Lange 2.
OTHER EXAMINERS:
F. J. Cresenzo, Reactor Engineer Examiner B. K. Hajek, NRC Consultant L. Kolonauski, Reactor Engineer Examiner 3.
EXIT INTERVIEW DETAILS Personnel Present at Exit Interview:
NRC Personnel F. J. Crescenzo, Reactor Engineer Examiner L. Kolonauski, Reactor Engineer Examiner D. L. Lange, Lead Reactor Engineer Examiner R. L. Turner, Reactor Engineer Examiner W. Raymond, Senior Resident Inspector NRC Consultant
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Brian Hajek, NRC, Consultant Examiner
Facility Personnel l
l W. P. Murphy, Vice President and Manager of Operations D. Reid, Operations Superintendent
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E. Lindamood, Operations Supervisor A. Chesley, Simulator Supervisor P. Alter, Instructor E. Harms, Instructor i
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Summary of NRC Comments made at Exit Interview The facility was informed that there would be no results of the current examinations available until after the grading of the written exam and after the in house QA efforts.
Every effort will be made to have the results within 30 days.
The NRC expressed appreciation for the use of the simulator for examiner familiarization during the week previous to the exam w~eek.
The NRC indicated that more attention should be given to making the candidates aware of the procedures that were available for use during the exam process. A weakness in this area was noted.
The NRC noted a considerable improvement in the material that was sub-mitted for use in preparing the exam, compared to that submitted a year ago; however, improvement is still needed, particularly in the order and indexing of the material sent. The depth and completeness of the system lesson plan resulted in exam preparation difficulties for certain systems.
The need was emphasized for training between now and the planned startup, after the long outage, with particular attention to E0P's.
It was indi-cated that, even though the simulator still needs work before it is suitable for examination purposes, it is still a very good tool to use for E0P training.
It was also mentioned that the NRC would be back to the site before the end of year to assess progress in the requal program and simulator status.
5.
Summary of Facility Comments at Exit Interview:
The facility expressed appr(c'ation for our efforts and accepted our explanation as to how exam resuits were to be handled.
6.
CHANGES MADE TO WRITTEN EXAM During the exam Question 5.11 was changed to require only identification of heat inputs and outputs to the reactor system.
The typo in Question 6.09 c was corrected from 39 A to 89 A.
In Question 7.08 the level at which steam cooling is required was changed from -37 to -87 to correct a typo. On Question 8.02 the valve position was stated to be open. These were changes made during the exam on 6/2/86.
Attachment:
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Master copy of the examination and the answer key (SRO).
2.
Significant Changes to the Answer Key, o
ATTAChinenf }
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NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_ygBMQNT_YANKgg_______
REACTOR TYPE:
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DATE ADMINISTERED: _Q6296L92_ _
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EXAMINER:
_IUBNEBi_Bz___
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APPLICANT:
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Sh_/3b_______
INSIBUgIlQNS_IQ_6PE61g6 NIL use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
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 be picked up six (6)
hours after the examination starts.
% OF CATEGORY
% OF APPLICANT'S CATEGORY
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THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
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PLANT SYSTEMS DESIGN, CONTROL,
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AND INSTRUMENTATION
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PROCEDURES - NORMAL, ABNORMAL,
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EMERGENCY AND RADIOLOGICAL CONTROL
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ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS
_2Zt99__ 199 99
________ TOTALS
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FINAL GRADE _________________%
All work done on this examination is my own. I have neither given nor recei ved ai d.
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dPPLiCEUT S SIGUdTURE
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5._ THEQRY OF NUGLgAR_EQWER_ELANT_QEERATIQN _ELUIDSz_ M Q PAGE
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QUESTION 5.01 (2.50)
Assume the plant had been operating at full power for one month and then scrammed. The plant went through a normal cooldown and stayed shutdown for ten days. Given the following curve plotting delta k/k versus time, answer the following:
a) At point 1,
list five contributors to the negative reactivity?
(1.00)
b) What causes the reactivity change between points 2 & 3?
(0.50)
c) What is required for the shutdown margin according to Tech. Spec? (0.50)
d) What causes the increase in negative reactivity between points 4 and 5?
(0.50)
-10
-9
% -8 1.1 DK -7
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k -5
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10 DAYS (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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i QUESTION 5.02 (3.00)
When the reactor is at full power, a spurious trip of all f eedwater pumps occurs. Indicate the immediate and long term response for the following parameters,(increase, decrease, constant) Explain reason for each response.
N, 1.
Reactor pressure 2.
Reactor level 3. Reactor core flow 4.
Turbine steam flow 5.
Reactor power level (3.00)
OUESTION 5.03 (2.00)
When the reactor is operating at 70% thermal power, how are the following parameters changed by a ten percent increase in core flow.
(2.00)
a) boiling boundary
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b) core reactivity c) power l
QUESTION 5.04 (3.00)
l Vermont Yankee's reactor is operated within three ( 3) speci-l fied thermal limits. List each of the three li mi ts 'and explain the specific phenomena that =ach limit protects against.
(3.00)
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_ THEORY OF NUCLEAR POWER PLANT OPERATION,..flyJQQi_AND PAGE
IBEBMQQYNAMICS i
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1 QUESTION 5.05 (2.25)
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For each of the pairs of conditions listed below, state which condition would have a GREATER ROD WORTH and briefly EXPLAIN WHY.
a.
Reactor moderator temperature of 150 deg.F or 500 deg.F ?
(0.75)
(assuming core flux is constant)
b.
For an inserted rod next to a fully withdrawn control rod or next to a fully inserted control rod.
(assuming core flux is constant)
(0.75)
c. For a rod at position 10 or position 40 in a core operating at 100 % power.
(0.75)
OUESTION 5.06 (2.00)
Regarding MCPR (Minimum Critical Power Ratio):
a.
At Vermont Yankee an unique MCPR limit is established to ensure that the fuel clad integrity safety limit for the plant is not exceeded for any normal ( operational ) frequent transient.
Based on this, which transients would most likely limit operation because of MCPR considerations ?
( three required )
(1.50)
b.
Why must the Tech Spec MCPR limit include a K factor when core flow is less than rated.
(0.50)
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QUESTION 5.07 (2.00)
Regarding reactor startup:
a) Does the magnitude of the initial level of source range counts af f ect the estimated critical rod position? WHY?
(1.00)
b) How long will it take to reach O.08% power if the reactor is supercritical with a 60 second period and at 0.02% power assuming the 60 second period is maintained until the 0.08%
power level is reached. (SHOW ALL WORK)
(1.00)
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i QUESTION 5.08 (1.50)
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The radiation level in the vicinity of the MSIV'S is normally very l
high due to the radioactivity caused by one particular isotope.
a) What is this isotope?
(0.50)
b) How is it produced?
(0.50)
c) Why is it not present in any significant quantities in the Off-Gas holdup piping?
(0.50)
DUESTION 5.0c (2.75)
For each of the events listed below, state WHICH reactivity coeff icient will respond first, WHY it responds first, and if it sads positive or negative reactivity.
a.
SRV opening at 100% power, (1.00)
b.
Rod drop at 100% power.
(1.00)
c.
I sol ati on of a feedwater heater string.
(0.75)
QUESTION 5.10 (2.00)
Ccre orificing is used to assure the desired flow distribution to esce Auel bundle.
at ENolain how the resistance to flow changes as the power increases in a +uel bundle?
(1.00)
b) Wh+
is the major purpose for the two zone or1.ficing plan.
(1.00)
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$*'4 CATEGOPY Mi CONTINUED On rJE 'T P9GF
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5 __IME98Y_DE_suC6568_E0 WEB _668MI_gEEB8IlgNz_ELUIDS _8ND PAGE
1 IHEBdgDYU8 digs OUESTION 5.11 (2.00)
A heat balance has to be performed on your shift due to a computer software malfunction. Using the following information determine the (2.00)
core thermal power.
6400000 lb/hr MFW
= feedwater flow
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110000 lb/hr cleanup demin flow MCU
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6423000 lb/hr steam flow
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23000 lb/hr MCRD
= CRD flow to reactor
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345 Btu /lb enthalpy of feedwater HFW
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506 Stu/lb HCU,IN = enthalpy cleanup flow in
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419 Btu /lb HCU,0UT= enthalpy cleanup flow out
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1194 Stu/lb HG
= enthalpy of steam
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68 Btu /lb Hcrd
= enthalpv of CRD flow to reactor
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26500000 Btu /hr
= recir. pump energy input
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Op 2040000 Btu /hr heat losses f rom rieclear boiler
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Ofl
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solve for reactor core t h erraa l energ/ input
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Qcore
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PLANT SYSTEMS DESIGNu ggNTR_Q L _AND_INSTRUL1ENTATIQN PAGE
I OUESTION 6.01 (2.00)
Concerning the Average Power Range Monitor (APRM) System, indicate TRUE or FALSE for the following
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a) Each APRM uses 20 LPRM outputs to compute average power.
(0.50)
b) Each APRM provides a f1ow biased high power scram at
.66w +54% where w is the total core flow in percent (0.50)
c) The APRM's provi de fixed scram trip points regardless of the reactor mode switch position.
(0.50)
d) If a cirruit card is pulled from one of the APRM drawers, a scram and rod block signal will be generated regardless of reactor mode switch position.
(0.50)
OUESTION 6.02 (3.00)
During op e-r a t i on, the reactor vessel wa t er-level drops from 162" to 80" due to complete loss of feedwater pumps. What automatic actions would be initiated by this change in level? Give approximate level trip setpoint and list system actuations and rspenses.
(3.00)
QUESTION 6.03 (2.00)
The Main Steam Line Isolation Valves (M51V's) are required to close in not more that five seconds and not less than three seconds. What is the basis for selection of each of these times'
(2.00)
GL'ESTION 6.04 (3.00)
Tlie Electrcnic Pressure Regulator ( EPR:). the Mechan 2 cal Pressure Regulatnr (MPRi and the Bypaes Ooening J ecl-t. E O J )
are all ccroonrmts at the Turbine Hydraul3c Cantral Svater.
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each of the Folicwino.onditionc and "cw n it cont-o]]1,g ( a) Durinq stretup?
I b) Durinq fv]1 oover operat,nn'
\\ c) Durina pre ocur t :ati c.n of the reactcr~
c.Oo)
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6-PLANT " YSTEMS DESIGN _QgNIRQL _AND_INSIRUMENTATigN PAGE
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:pected to respond to an SRV discharge line vacuum breaker STICKING OPEN during actuation of the SRV? Bri e f l y, JUSTIFY your answer. (1.00) ri**e .: A T E _ ';t i v e. CONTINUED Or . a:E r****; ~ r r _-
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r 6 __PL@NI_SYSIEMS_DESIGU1_CQUIBO6t_@ND_INSIBUMENI@IIQU PAGE t l l 't' OUESTION 6.07 (2.00) Consider the situation in which the reactor is operating with both , Recirculation Pump M/A Stations in manual because the Master Controller ' has failed full scal e high. Reactor level is within the normal band, and may be considered to stay there for purposes of answering this question. Assume an operator inadvertently transfers the "A" Recirculation Pump M/A Transfer Station to AUTO. Exclain how the Recirculation Pump speed will change (increase, decrease, or remain the same), what the final stable speed will be and the reason for this speed change if , a) The total feed flow is 20 percent, and (1.00) b) The total feed flow is 20 percent. (1.00) OUESTION 6.08 (2.00) The Diesel Generators are designed to aatomatically start on receipt of undervoltage or certain plant emergency signals. Because they are emergency backup syetems, they are also designed to be operated manual l y for pericdic testing, a) If a DG fails to start (doesn't reach minimum speed, the engine is stopped and " Locked Out". Where the "Loct Out" reset? (0.50) .= b: Fcr parallel operaton of the DG's d u c i r.g testing, the droop s e t t. i n g 19 different frcm what it - for normai, or isochronous, aceration. Why 3= there a di+seren:e in these setti gs7 (1.50) c '_" :' ' N M C '. N FM1
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C c,T E GDP s " gA . . 6. PLANT SYSTEMS DESIGN _CQNTROL1_AND INSTRUMENTATION PAGE 1 ! OUESTION 6.09 (1.50) l Several precautions are to be observed in Shutdown Cooling mode. What could be the consequences of not observing the following precautions? ' , a) When starting the RHR System in Shutdown Cooling mode, flow is not increased to 2000 gpm within 10 seconds. (0.50) b) The power supply breakers are not opened and tagged to assure that RHR 26A(B) and RHR 39A(b) valves remain closed. (0.50) c) The RHR .A(B) controller is placed in MANUAL. but the valve is positioned at only 35 percent open. (0.50) DUESTION 6.10 (2.00) Fc-the HPCI sytem: a) When must the keylock bypass switches be in the normal position? (0.50) b) Why must MOV-25 (mini mitm flow line) be closed / checked closed following a HPCI turbine trip or isolation? (0.50) c) Why must MOV-15 (inboard steamline isolation valve) be closed tefore closing MOV-lo (outboard steamline isolation valvo)? (0.50) What is the mmtimum di f f erenti al pressure above which MOV-15 and 16 should not be opened? (0.50) NE3 TION 6.11 (2.00) 'e CPCCW System provides cooling to several essential and non-
- -tr
the Rca. actor Dutidinq. .u 15 t h r> to mper at ur r. of the water in tae PBCCW System
- o l c - ci -
<1.0 ) - - :... ac the t amperat ur 'of individual component cooled Dv FECCL c. stem r egu l at erJ ' ( '. u ~' ) I f ***** END GF ZATEOOR" r'* 4**Aa h - M - ' . 7. PROCEDURES - NORMAL ABNORMAL _ EMERGENCY AND PAGE i eeolg60GICeL_CQNIBQL
t l i OUESTION 7.01 (1.50)
While the reactor is at 70% power, one recirculation pump trips. l What two immediate acti ons are required? (1.50)
QUESTION 7.02 (2.00) During 100% power operation, there is a unexpected decrease in condenser vacuum at a one inch per hour rate. What are the two immediate operator actions. (2.00) OUESTION 7.03 (2.00) What are the two entry conditions for RPV LEVEL CONTROL? (2.00) (per OE 3102) GUESTION 7.04 (2.00) What are three Shift Supervisor responsibilities when he is called upon to approve an RWPO (PER A.P. 0502, RADIATION WORK PERMITS) (2.00) OUESTIGN 7.05 (3.00) During operation at power, a feedwater malfunction occurs causing water level to increase rapidly. Accordingly to OT3114, Reactor High Level - Fracedure: a) Whv must the operator close the MSIV's and verify the rractor han scrammed when level is rieing above 177" (1.no) " b) What mutomstic trice eihoul d have occarred at 177"' ?,on) t+t*** C.'i E GOP u o' COrjTIr1UED ON NErT PAGE t*$tt' 6j-g - I Zz__PBQGEDUBES - NORMALt_ABNQRMAL _ EMERGENCY AND PAGE 1 E6 Dig 6QQlG66_GQNIEQL OUESTION 7.06 (2.50) , i The entry conditions for OT3121. INADVERTENT OPENING OF A RELIEF VALVE Procedure, are any indication of an inadvertent opened SRV. What are five of these indications? (2.50) OUESTION 7.07 (2.00) How does having or not having a completed NRC Form 4 affect the amount of radiation exposure one is allowed to accumulate while working at the Vermont Yankee Nuclear Power Plant with respect to whol e body exposure 7 (2.00) DUESTION 7.08 (2.50) Procedure OE-3102 "RPV Level Control" will direct the operator to steam coni the reactor it all possible injection into the reactor becomes unavailable and level drops below -37 This is accomplished by opening noo SFU. If during steam cooling, RPV pressure drops below 700 psig.the 0~_edure directs the operator to emergency depressurire. What is ' ;n'_rtcant about 700 psig and why is PPV depressurization required t t] w 700 p -i o. (2.501 ' ESTION 7.o9 (1.50) 1r..r : 1 tem,,erature should e::ceed the limits imposed by the "FPV - -: r.t;:n Curse" of procedure OE 3103, the operatcr wi}l be r -t oe to do an energency depressurtration and then 41 occ4 t h c- -- .h - it F"e basis -or PPV emergency deprecturization in thte - 'I.50' s**** CLTOGORY 07 QNTINUED ON NEXT PAGE *****/ Akt - . ' Z1__EBgCEQUEES_ _Ng8d@Lt_@QNgBd@(t_EDE8GENCY_@ijD PAGE E891969GIC66_GQNIBg6 OUESTION 7.10 (1.00) Procedure O.P.2181 " Service Water /Alte-nate Cooling Procedures" cautions the operator not to place more than one non-operating service water pump in the AUTO mode. E.: pl a i n why this caution exists. (1.06) ' l OUESTION 7.11 (2.00) During a reactor start up to criticalltv, a sustained period of less than 30 seconds is attained. What actions should the operator t a ':e as a result of the short period? ( 2. ':-0 ) (Consider immediate action and administrative notitications). QUESTION 7.12 (2.50) Procedure G.P. 0111 cautions the cperator to limit stack gas release rate to less than the Tech. Spec. Limit. Why is this caution emphanized during the shutdown /cooldown evolution? (2.50) I i,4., un or w rgerm <c 134,, F V - . hV( ' D___8DDINISIB@IlyE_BBQCEQUBESz_C.QNQlliQNS _@NQ_LidlI@IlgNS PAGE t . QUESTION 8.01 (1.50) Is an SRO required to be present on the refuel floor for the change out of an LPRM detector? WHY OR WHY NOT? (1.50) OUESTION 8.02 (2.00) Following a surveillance, the #3 TIP ball valve did not auto close. The TIP machine requires extr.a jogging to close this valve due to a malfunctioning (sticking closed) inshield limit switch. IS primary containment satisfactory? IF SO WHY9 IF NOT WHY NOT and HOW can it a be made satisfactory? (2.00) OUESTION 8.02 (1.50) According to the Licensed Operator Training program under " emergency exposure" it states that " judgement sh al l be le4t to l persons in charge of emergency operations to determine ma :imum exposure". What are the suggested maximum exposures for the following? 1. To save li'e (0.50) 2. To save equipment and propert,s (0.50) T Where e-;posure occurs ,r a "olanned emergencv" ect: r (0.50) 7INJED CN NEYT t M E-i 's= t*e4
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. y . e __@pblNi@IE@IlyE_ESQCEQU6ESt_CQNQlligNS1_@NQ_61dlI@IlgNS PAGE i ' OUESTION 8.04 (2.00) According to 10 CFR 50,-the reporting requirement of ONE HOUR for the following conditions is applicable. [TRUE or FALSE] A. The plant is in a condition not covered by operating and emergency procedures. (0.5) B. The loss of the offsite notification system. (0.5) C. A valid automatic initiation of the Reactor Protection System (RPS). (0.5) D. A shutdown was commenced because the plant was in violation of the rechnical Specifications. (0.5) OLtESTION 8.05 (2.00) 1. Administrative Procedure A.F. 0036, Shift Staffing, requires that a licensed reactor operator or senior operator be within line of sight at all times in the CR. What does this mean? (0.50) 2. What are the minimum shift staffing requirements during startup and operations for the Operations Department? (1.50) OUESTION 8.06 (2.00) need 'v'e r mon t Yankee Plant is in a refueling outege end therc is -- to replace cne control rod. What conditions per Technical Spectfi-cations must be satisfied prior to DYPASSING the refuellrg interlock to permit removal of the control rod b l a d e (Document your answer usi ng the attached Technical ke:1 fica *1ons) (2.001 OUESTION O. T ' ?. '3 0 ' % r=actcr tt a n c r e * i n _; a* tc gower when a'. Mi* . :: -er G.' . 4 review o' the alar nr t r * c-mow e the reactcr sc's-s-c- 1 G r' high tlu>. Dosa. thi+ violete Technical Spectfitatir : ~ (Documont mur n s v.er basrd cr thr r-, t t a c h e d Tech, .3: Sp ec t f I c a t i en c,. ) ( 1. U n4446e c c T E,00p, r i;: r r*ji IMUE E C* r'E r ' ~ 1-
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- . et__egu1NISIB@IlVE_EBQCEQUSESz_CQNQ1IlgN$1_@NQ_LidlI@IlgNS PAGE OUESTION 8.08 (1.50) In accordance with the Technical Specifications, the reactor was scrammed due to Suppression Chamber water temperature being greater than 110 degrees F. The reactor is now in HOT SHUTDOWN, Suppression Pool Cooling is ON, and Supprescion Chamber water temperature is 102 degrees F. MAY YOU STARTUP THE REACTOR AND SWITCH THE MODE SWITCH TO RUN? (Explain and document your answers using the attached Technical Specifications.) (1.50) DUESTION 8.09 (3.00) a) According to procedure CN3151 off gas explosten, what two overall adverse plant conditions would be of greatest concern to the Vermont Yant ee Operating Shif t" (1.00) b) What steps should be taken if an offgas explosion occurred on your shift and there are indications that the rupture disc has been fractured? (2.00) GUESTION 3.10 (1.50) What three immediate actions would /ou take on receipt of impending hurricane from Civil Defense authorttles' 1.5C OUESTION 3.11 2.001 According to A.F. 0140 Vermont Yanlee Local Control Litching Fules. . What are tun of the four "Pe=toration Conditions" noted in that documnnt that valvee er breaker pos)tions murt ccn' arm ta teforc tage can be cleared' '2. <si?*1 r '. I E.c ; R, C o m ,'1 D ' :N *FrT F -. T
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. ) Sz__GDd1NISIB8I1YE_BBQCEQUBES1_QQUQlIlQU$t_@NQ_LidlI@IlgNS PAGE ) OUESTION 8.12 (2.50) In the event you are called on to classif y an emergency condition, what , basi s would you use to differentiate between: a) An alert and an Unusual event and which would be considered the more e:: t r eme? (1.00) b) What differentiates between a site or a general emergency? (1.00) c) As a shift supervisor when are you relieved of the responsibility of emergency director' (0.50) OUESTION 8.1? (2.00) A temporary change to operating proce v ez may be made provided the change in approved by two SRO's. a) What are the administrative requiretents following the above action' (1.00) b) Are the requirements different for temporary changes to radiation control procedures") (1.00) ($ttts E N r. ~ ' c1 m
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- , 5:__IBEQBy_QE_NUCLEOB_EgWEB_E60NI_QEEBSIlgNt_ELylQSz_@NQ PAGE IbEBMODYN@MICS ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. ANSWER 5.01 (2.50) a) 1) Control Rods 21 Mcd. Temp. React. Caetf. contrtbution at 545 deg.F=(-47 delta k/k) 2) Fuel Temp. React. Coeff. (doppler) at 545 deg.F=(.4% delta k/k) ( - 2. 7 '/. delta k/k) 4) Xenon = b) Samarium from decay of promethium =( .4% delta k/k) (.20 each) (1.00) t.25))interactingwith the negative bi(P'ue reactivity trom cooling rsactivity being added by Iodine decaying to Xenon.'.25) (0.50) c) Shutdown Margin required by Tech. Spet. 4.3.A.1 /---demonstrate a shutdown margin of 0.25 per cent delta L at an, time---- with the highest worth operable control rod withdrawn----) (0.50) di Samarium buildup from decay of Promethium. (0.50) REFEFENCE Ver ncnt vaniee Niiclear Power Station; SCRO-02-013 THROUGH 018. . c ' /b1 l - Sz__IBEQEy_QE_NUC(E8E_EQWEE_Eb@UI_QEEE@llgN1_E(ylQSz_69Q PAGE le i IbEBdQQYU8 digs ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. ! _ i ANSWER 5.01 (2.50) a) 1) Control Rods 2) Mod. Temp. React. Caetf. contribution at 545 deg.F=(-4% delta k/k)
- ) Fuel Temp. React. Coetf. (doop l er ) at 545 deg.F=(.4% delta F/b )
(-2.7% delta k/k) 4) Xenon = 5) Samarium from decay of promethium =( .4% delta k/k) (.20 each) (1.00) b) Plus reactivity from cooling (.25) interacting with the negative reactivity being added by Iodine decaving to Xenon.(.25) (0.50) c) Shutdown Margin required by Tech. Spec. 4.3.A.1 f---demonstrate a shutdown margin of 0.25 per cent delta k at any time---- with the highest worth operable control rod withdrawn----) (O.50) , d) Samarium buildup from decay of Promethium. (0.50) REFEFENCE '/er men t vantee Nuc1we Power 3tation; SCRO-02-013 THROUGH 01 h n/l ' ' Uz__IBEDBY_DE_NyCLg@8_EQWER P69dI_QEE8@I1QN _E(y1QS _@NQ PAGE z ! IHE8dDDYNedICS j ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. q I i % $ ANSWER 5.02 (3.00) i C oJJ olt*M T - w erH Cx M SWt t9) ! 1. Rx Pressure - Decrease e.
- ).
Reactor power decreases and [ pressure follows the power decrease,after the main steam . line isolation valves close, decay heat gradually causes the i pressure to raise until the relief valves open (.)2TI. -be t no g (0.75 ema nzi se overpressw emccurs i.Z5). Decrease (.25). causing a reactor low water 2. Sensed Rx Level - level scram at about ( 8 seconds) and initiation of RCICS, HPCI and isolation of the main steam lines (in about twelve second) on the low low sensed level trip (.25), level stabilizes as controlled by RCIC (.25). (0.75) 3. Core flow - Decrease (.25). Due to loss of feedwater (.25T and rundown of the recirculation pumps to 207. speed (.25). ( 0. 75 )' 4. Steam flow - decrease (.25). Due to power reduct:en(.25). (0.50) 5. Power level decreases. Due to voids initially on flow i reduction (0.25) and then due to the scram. ( 0. 2,5 ) REFERENCE Vermont Yankee Nuclear Power Corporation, FSAR VOL IV. 14.5.4.3. Loss of Feedwater Flow. LOT-05-109, Feedwater System; LOT-03-007, Reactor Recirculation System ANSWER 5.03 (2.00) a) The boiling boundary moves further up the core sr.d moderator ' has now replaced some of the voids (.50). The re-ultar.t cower
increase causes increased boiling and the bo111 ; boundary is '
lowered to near its original position (.50) (1.00) b) Increased modcration adds por.itive reactivits the core. (0.50)
- -
Increase (along the constant rod positi:-. : " e) $. e to l, c) P o w e.- the change in core flow. (0.50)
-
' REFEPENCE Vermont Yankee Nuclear Pcwer Corporation LOT-03-007.Pg 58/50; Cecirculation Flow Control: SLO i !~ ' . . Dz__IBEQEY_QE_bgGLE88_EQWEB_EL@NI_QEEB911gN _ELQ1QSt_8NQ PAGE z IHEBdQQyN@dlGS ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. ,. , ! i ANSWER 5.04 (3.00) I a a) Linear Heat Generation Rate (LHGR), designed to limit fuel cladding (plastic) changes in dimension to less than 1% (of
the diameter of the fuel cladding) by limiting the amount ' of heat that may be generated in the fuel. (1.00) b) Minimum Critical Power Ratio (MCPR), protects against the onset of transition boiling. (1.00) , i c) Average Planar Linear Heat Generation Rate (APLHGR), limits the planar heat generation late so that in the event of a LOCA, the peak clad temperature would be less than 2200 degrees Fahrenheit. (1.00) REFERENCE Vermont Yankee Nuclear Power Corporation SCRO-01-208, Fuel Cladding; SCRO-02-311, Transition Boiling and Atlas Tests: VYNPC Technical Specifications 3.11 ' ANSWER 5.05 (2.25) a. At 500 ceg.F (0.25),As moderator temperature increases, neutron leakage out of the fuel bundles is increased. The control rod is exposed to a higher neutron flux, thus rod worth increases.(0.5) (0.75) b. Next to the withdrawn rod.(.25) neutron flun is higher in t h i,s area thus rod worth is greater.(0.5) (0.75) ( Q GQg) Lc10hw, AsL, $OL, Of Y Y f * WW At positten 10(..v Volds at the top allow more fast leakage c. , and lese tnermal neutron flux,thus greater rod worth at the bottom. . ?. ) (0.75 REFERENCE ~- 4.. : 1o+- Pcwer Corporation: SCRO-02-016, Control Rod Worth Vermont Yant . A . . D __IMERBY_QE_ NUCLE @B_EQWEB_EL8NI_QEEB8IlgN _ELylpgs_8NQ PAGE i l IBEBdQDYNedICS t ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. ) i i ) ' ANSWER 5.06 (2.00) Y J a. Turbine trip or generator load rejection without bypass. (0.50) Loss of feedwater heating. (0.50) ' )) I (0.50) controller failure ( maximum demand (Feedwater ( b. To make the MCPR limit more conservative to account for the possibility of a sudden flow increase and corresponding power increase. (0.50) , i ! , REFERENCE Vermont Yankee Nuclear Power Corporation VYNPC Technical Specifications 3.11.C. , ANSWER 5.07 (2.00) I a) No (0.50). The critical control rod position is a function of
I the Keff or reactivity of the reactor and is not a function of the source count rate (0.50). (1.00) b) P = Po e(t/T) In P/Po = t/T . 01-83 4 Loc t=T* In P/Po = 60 * In.08/.002 = 60 * 3.69 = 221 seconds (0.5 equation. O.3 calculation, 0.2 answer) (1.00) REFERENCE Vermont Yankee Nuclear Power Corporation, SCRO-02-010, Reactor Theory ANSWER 5.09 (1.50) =) N:trogen 16 (.5). -- F ) p cduced by the activation of oxygen in the reactor water (.51
- ) N-it deca.s with a half life of 7 seconds so it is decayed by the t 2 ne it l eaves the betwell. (.5)
(1.50) . CECEFINCE Vernant Yanteo Nuclear Pcwor Corporation. SCRO-02-010. Reactor Theory F }V\\s
t 5 __IHED8Y_DE_NQCLE@B_EQWEB_EL@NI_QEE8@IlgN _ELUlQSz_@NQ PAGE z g t IHEBdQQYN@dlGS - ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. a , ANSWER 5.09 (2.75) i A. Void Coefficient (0.50), Decreased pressure causes an increase , in voids (0.25), adds negative reactivity (0.25). (1.00) B. Fuel Temperature Coefficient (0.50), The rapid addition of ' ! positive reactivity due to the rod removal causes power to increace therefore fuel temperature increases (0.25), adds negative reactivity (0.25). (1.00) C. Moderator Temperature Coefficient (0.25), Removal of feed heating causes a decrease in feed water temperature (0.25), adds positive reactivity (0.25). (0.75) REFERENCE VYNPC; SCRO O2-011 THROUGH 015, Reactivity Coefficients ANSWER 5.10 (2.00) a) The orifice mounted in the fuel support piece adds a relatively large dp to the fuel element flow path so that the change in dp caused by a phase change in the fuel bundle is Emall compared to the overall dp of the fuel element flow path. (1.00) b) Peripheal fuel elements are orificed tighter in order to drive more flow to the higher power central fuel elements. (1.00) REFERENCE VYNPC; LOT-03-OO1. Pg 15, and SRO Upgrade exam. 8/30/86, C #9 SLO 1 ANSWER 5.11 (2.00) _ Midan QA W - f_a***9
_ . ' Ocore = MG x HG + MCU(HCU IN - HCU.OUT) + Ofl - MFW n HW -.r - MCRD x HCRD ( 1. tXr k 2307'S 1194 +110000(506-410) + 2040000 - 64000' ~35 6423000 Occre
= , -2tSOOOOG - 23000 68 = 5444500000 Btit/hr = i t' c" r..+ (l.On-
t REFERENCE ' Vermont Yankee Nuclear Power Corporation. SCRO-02-115. Reectcr Hrot Balance g -- - - -- . - ..-. ._ . . I 6 __ELONI_SYSIEdS_QESIGN,.QQNIBQLt_@NQ_INSIBQUENI@llgN PAGE ( 1 , ' ANSWERS -- VERMONT YANKEE 86/06/02-TURNER, R. - ) l ANSWER 6.01 (2.00) ' I a. true i b. false i c. true ! d. true I (0.50 for each correct) ! ' REFERENCE VYNPC; LOT-03-106.Pos 12-15: SLO-1,3. ' . g 2.- ( + ANSWER 6.02 (3.00) Level Action , 127" RP Scrom. PCIS Gr. 2(a),3,4,5 actuated [27 (1,00) ( 82.5" RPT/AR1 10 sec. T.D.; PCIS Gr. 1 2' 3 . RCIC start: . HPCI start: LPCI start; CS star : AD3 S gr,t: DG start; t I Main Gonerator.Lnctout; Drywell RRU's trip; UPS, feeder 6ceater trip; (.25 each tip to 2.bol ' bow. s h. W M ( 2. 50)
I (6%) Alaba pl4444C ' /v.u tl4 ' REFERENCE VYNPC; LOT-03-CO2, Pg 22, Peactor Vessel i nstrumentation: SLO 3 ANSWER 6.03 (2.00) The ma::imum five second time was chosen to limit radioactive release to within acceptarle values. (1.00) The minimum threr second time was based on anal yses that showed a less severe reactor ; r sore transient than that calculated for a turbine trip without be - valve operation. - (1.00) FEFERENCE
VYNFC: LOT-05-1-l' f * * + c. 9. *. e m 9LO - % 4w _%g L do-~ ~R(>$ A~t t4v - - ( [s M LLMs*d ellbf 'l}d V
m & wM. m g,_ ,,,.3,7 .. ,, . ,-,-r- .--7.c.--,- .-,.-.e- ,,,.,,--..--y------r-_--.r,--.+---m- _m-vwvm-,----,--.-v..--.-,...------~,,,,.,----------.,v ,---.>--,,---.%, = - - - - . - , . . bz__E68NI_SYSIEdg_QEgigN _QQNIBQ(t_8NQ_INSIBUDENI@IlgN PAGE 2 ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R.
ANSWER 6.04 (3.00) a) The Bypass Opening Jack is used to bypass steam to the ' main condensor during plant warmup and startup by manually controlling opening of the bypass valves. (1.00) b) The EPR is the normal operation controlling device (and it's setpoint is set at 965 psig as measured at the turbine stop valve inlets. As reactor pressure changes the EPR signal, through the pressure torque tube, causes the turbine control valves to open or close to load or unload the turbine,% (1.00) c) The MPR ts used to operate the turbine control valves, through the pressure toraue tube, at steam line pressuren from 150 to 1050 paig. The setpoint to adjusted from control room parml CW 4-7 thrcugh tht-motor mounted on top of the MPR in the iront standard. The MPR is used to control until the setpo1** 1-edjucted to above the EPR setpoint for normal operation 5. + which time control transfers to the EPR. (1.00) REFERENCE Vermont Yankee Nuclear Power Plant, LOT-05-OO4.Pgn 12-15. MHC System SLC) 2 ANSWER 6.05 < 1. 5' n The Reactor E" ' : 1 d i n g Venti 1ation system is shutdown (.5) and the Standbv Gan Treement Svstem in started (.5) and in addition the hich radisti-" =1gnal is snot out to the Prtmary Containment and the Reac tor-Vessel Isolation Control system to initiate closure of the 'arious ortmary and cont ai nment purge and e :haus t paths (.5). (1.50) . FEFERENCE VYNFC: LOT- ".F ~ ' ", Frecess R+diation Monttoring; SLO ; ! . , t V - - 6 __ELGUI_SYSIEMS_DESl@N _QQNIEQLt_@NQ_lySIEgMEUI@IlQU PAGE 1 ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. i \\ ANSWER 6.06 (2.00) a. Following the SRV's first actuation, the steam in its discharge line would condense causing a vacuum in the line (0.33). This would result in suppression pool water being drawn up into the line (0.33) which could cause overpressurtra'.lon of the line on the next actuation (0.33). (1.00) b. Increasen (0.5). The open vacuum brealer provides a direct path to the drywell for the steam entering the SRV discharge > linn (0.5). (l.00) EEFERENCE UYNPC: LOT-OS-101. MAIN STEAM SYSTEM: SLO 3 ANSWER 6.07 (2.00) a) The pump speed will stay at the minimum speed or go to the minimum speed because the low speed limiter is controlling speed as 1ong as total +eed +1ow is l e s e, then 20 percent. (1.00) b) The pump npned will gc, to the high speed limi' of the Master Controller Speed $emand L.imiter (102 percent) because with feod fIow 20 percent and the pump dischargo valve fulI cpen, the low speed limiter 1r taparted. (1.00s - w a <m p.~ GEFEFENCE 'lY NF C. LOT-'C-OO7. Rcactor Recirculation S/ stem. NE u h pTd(d ' VYNPC System Description. Fig 11. SLO 7 ,,,;..y w - y ' r. J '! ,,, 4 4,,
o-L'. o 2. .fs isoc)<oso s, iron,arre } *l l o p ere /te,s s, +de 0,/ C, ca,W I. , pali, lia, lls $ss bepe.s <y Jan e sier, +A e a.rs wer },. p <l ( ), i,.,., h e, /Ja ' +), < 3 sind e D)& <o.ia/ cc.- 4.1 y io/ -G.*pueecy J :/ ~e,< o,,e,:, /ca/ o-1J y,/ct urM a.e<. d,<p.,. rf spee<! dr.sp rs.e / e yO u) - in ,. . Ile I unA a,. He, u,rd suc1 ila f il /.od w<< < lls, ><.pe, A...a l fnereoseel /le Dl4, u. }e/ or, if ptek q $)a,e */ /)e /acc/ urc < a ll o S 'd< /oac/ c, ),c d wau/c/ i/ sp<< c/ de, we<<..:<J - f C. rha /o,,c-o ce ci, p <<= //e /. inaeJi.e ca., b./s frep,e.,ey w /e-u.)s a<<
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less.- /S f / d d.0 9 /bicr 7'/v <, loweve/, /.s 'e r l-d ,. se < e e/va r i/ ts I /, - ireyvi< ee / /-Ja.h +Ac. o,is, //o-va ls e e-C s e. ' '//s ' or as: , J < <., k < I k ,3, e. <.. ' u c. /,e / ' d.. u s. /c) L - ope,, a J. +h< /n v s,. . V '.<< t) * s k.r. w le el - 4. / < s.a l- .- son e e,r n : c / te : n :,.*.. el' l'.,e1 h - .c c. ,c s.o7 , - s'e .4. 4e x i s,i.. //L ,n e e.. lly y-i>,,, c~, n., e ' o ,
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- l
' '.'* # :: a.* * e CQn Ec!sie tr.sy' A s * /t'3 sc,e es o / A*n es \\ 9,,e c; I,'c. //y o. /), ida key b h nis,e s /s, -- e.
- --
. . , n, 9,0 0.0 h f d* e ** **. ***4'**.* ! ,o 64. l$[e k* ,. y Q* f ( f,, $ l,Ay*epe ./ / i /E ,, )c ? op 2isu a { f~ O ' ( 6. PLANT SYSTEMS-DESIGN _CQNTBQl=1_@NQ_lNSTEUMENI@IlgN PAGE _ t i ANSWERS -- VERMONT YANUEE-86/06/02-TURNER, R. I l. ANSWER 6.00 f2.00) a) The lockout must be reset at the local panel. (The specific lockout is first verified locally. The start failure relay is R2 which gives the start fat. lure alarm and Indication and also energizes the shutdown relav.) (0.50) b) There is a difference because at nero droop the frequency will be controlled by the DG.(0.5) An droop is increased, a second generator on the line, in this case, the main generator, is able to control the DG unit speed, and thus system frequency.(0.5) This provides for load sharing st4.bility. (0.5) (1.50) FEFERENCE VYNFC LOT-05-T00 Pg1 13. 38. 4d. SLO 2,4.5.f.') ANSWER 6.09 (l.50) a) The minimum flow valve would open and reactor water would be discharged to the torus. (0.50) b) If RHR-26 A(P) were open, water might be diverted to Drywell Spra-and 1+ M - w AiB) were open, to the Torus Sprav. (0.50) t) The heat e'cheN:E - reltrf valve might lift. (0.50) REFERENCE V y NF'C L O T-v;-70o, % 14: OF 21:4 Pqn 6 L15: SLO 3.4.0 6 RHP 9 ys t c.a Derer1ptton Figure 21 . .. . . 6 __PLONI_Sy@IEdS_QESl@N,_GQNIBQLt_@NQ_INSIBydENI@IlgN PAGE ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. I i ANSWER 6.10 (2.00) a) When reactor pressure is greater than 100 psig and less than 150fpstg. (0.50) b) To prevent the CST draining to the suppression pool (torus). (0.50) c) To prevent trapping condensate in the HPCI steam line. (0.50) d) 50 psid. (0.50) REFERENCE VYNPC. LOT-03-303. HFCl; OP.' 12 0, Pqs 4 10, 11.: SLO 6.a 6 6.d. ANSWER 6.11 (2.00) a) RBCCW System tenperature is adjusted and regulated by throttling service water flow through the heat exchanger. (1.00) b) Temperature of individual componentt being serviced i s rt>gul ated by u c,i n g the return globe valve from that component to adjust the flow. (1.00) FEFERENCE UvNFC: 0.P.2182. System Lesson Plan - RDCCW - , M . . j 7. PROCEDUBE@_ _NQ8M@Lg_A@NQEM@L2_EMg8QENCy_@NQ PAGE 2] 88D196001G66_GQNIBQ6 > ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. D f ANSWER 7.01 (1.50) 1 Single Pump Tr1p . a) Immediately shut the discharge valve of the tripped pump (0.75) to allow the pump to come to a complete stop. ' b) Reopen the discharge valve after several minutes to help maintain loop temperature. (0.75) PEFERENCE VYNPC: 01 7.119. Pg 1 Recirculating Pump Trip l ANSWER 7.02 (2.00) Immediate Actions: ' a) Start any idle circ. water pumps. circ. water booster pumps or cooling water fans as required. (1.00) b) If the cause can not be immediately detcrmined, reduce reactor power au necessary to maintain tc.c6 pretsure below 5" Hg. A E's. (1.00' FEFERENCE VYNPC: OT !.1 2 0, Condenser Low Vacuum - Procedure ANSWER '.03 (2.00) ,* 1. Lesel cannot t;e maintained ebove 1 : ~'. 't.W' ,I 2. Lt.vc' . a n r. n t et dat vmi-a:c. ( 1. n: 1 l! REFERENCE VYNPC; CF 7102 1'O PPV LEVEL CONTROL. ! L------ r s . . Zi__BBOGEDUBES_ _N9BM86t_0@NQBM@6t_EMEBGENgy_@ND PAGE j B09196901986_GQNIBQL I i ANSWERS -- VERMONT YANKEE-86/06/02-TURNEF(, R. I l i I { ANSWER 7.04 (1.50) ! } h sely attect plant Hiety. ' conflir_ts which may . 1. Review the scope of work for operational I 2. Review all plant conditions which may adversely affect the satety at toe assigned work party. 3. Give his approval for the work to start,when satisfied it can _ be pm iv men witn acequate safety to the plant and all plant ) personnel. (ExAcf lupfpjy6-400T b vtRO j Q (1.5m (.5 each> REFERENCE VYNPC; A.P. 0502, RADIATION WORK PERMITS ANSWER 7.05 (3.00) Above(217' the steam lines begin to be 'looded. (1.00) a) . A% 'N &p & b) 1. Main Turbine 2. Feed Pumps 3. HPCI 4. RCIC (.5 EACH) (2.00) REFERENCE VYNPC: OT3114 Reactor High Level - Procedure, Pg ANSWER 7.06 (2.50) ,. 1. Generator load reduction a4 12. t o 15% or bypass.s: se :;osure. 2. I n c r c= a s i n g torus temperature. 3. " Safety / Blowdown Valve Lea!" alarm. , A. Rx Relief Valve Open" alarm. + 5. Steam flow / feed tlow m 7. s m a t c h. , 6. 5RV indicator lights CRP
- --?.
(.5 each to 2.50) (2.50)
l- '!' REFERENCE VYNPC; OT3121. INADVERTENT OPENING OF A RELIEF VALVE EAOCEDJRE .- - _ - _. - - - - - ~ ,- 1a - - Sk [e Zz__B89GEDUBES_ _NQBD66t_6ENQ85961_Edg8QgNQy_@NQ PAGE RAQ1QLQQ1Q@6_QQNT8QL - i ' ' ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. y
, ANSWER 7.07 (2.00) , d. The allowable exposure is about half of that allowed without NRC j Form 4completionandkn any event is subject to ALARA ] ;p; considerations. (2.00) ' REFERENCE VYNPC; LOT-06-305,LRadiation Protection Standards, Table 1. ,
- n s
, ANSWER 7.08 (2.50) The minimum RPV pressure producing steam flow through one SRV sufficient to limit peak clad temperature to 2200 deg. F has been determined to be 700 psig. The surge of steam flow resulting f rom rapid depressurization will again lower fuel temperatures providing additional time to establish a source of coolant injection. (2.50)
'~ REFERENCE Vermont Yankee 3102 ANSWER 7.09 (1.50) I This curve i s an indication of RPV level indication accuracv. Should this curve be violated, RPV level will be essentially unknown. Therefore, to ensure adequate core cooling the RPV , (1.50) is depressurized and flooded. ( j gg ) REFERENCE VYNPC; OE 3103. Drywell Pressure and Tempe-a se Control Procedure l! li k iI . I , . .
Zz__E80CggyBES_ _NQBd@62_@@NQBd@(z_EdgBQENQY_@ND PAGE RADIOLOGIC @L_GQNT896 i d-ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. q 'i ! l ' ' ANSWER 7.10 (1.00) More than one SW pump starting at one time can cause water hammer sufficient to damage Diesel Generator piping. (1.00) REFERENCE
VYNPC; O.P. 2181 Rev 14 Pg. 6 , ANSWER 7.11 (2.00) Use " emergency in" to turn period. Insert rods to subcritical and notify SS, OS, & R.E. (2.00) REFERENCE VYNPC; O.P. 0100, Rev. 16 Pg. : ANSWER 7.12 (2.50) Decreasing reactor system pressure can cause greater fission necrtier-t release through the fuel clad due to the hign fuel rod internal pressure compared to the Icwering outside reactor pressure during shutdown /cooldown evolutions. Also since the mechanical vacuum pump is en line which does not exhauGt te off-gas filters. (2.50) REFERENCE EM A/4/y.ux ' VYNPC; O.P. 0111, Pg. 1. ! 'f , i . I . .- ._ _ _ _ ' . '
MEMORANDUM ' j .x.. . TO: J.p. pe11etf 6r ' Vern'on March'18, 1983 ' 'W.p. Erihf * * " ^ Brattleboro FILE #: ' '' ' ' co0M: I ,,JEC'T:' Revii164'1't6'T6ch. 'Sp4c. ' Interpretation No. 28 - SRO 6n[Aif0il 'F16of ' % ! . References: a) IE Circular No. 80-21. Regula' tion of Refueling ' Crews, dated September 10, 1980 - b}) A.P. 1000, Refueling, dated September 18, 1979 c Vermont Yankee Technical Specification, parag'raph 6.1.0.3 d) Report of Telecon, RES to TTM, dated 9/26/80
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e) Tech. Spec. Interpretation No. 28 - SRO on Refuel e Floor, dated September 18, 1980 L
. . f Diii0isiod Reference (a) stated that some Ifcensees had misinterpreted the regu-latory requirements applicable to fuel handling and attempted to clarify those requirements by stating that "the individual manipulating the fuel handling equipment over the reactor must be an NRC licensed Reactor Operator (RO) unless the facility technical specifications include provi-sions for the operation to be supervised by an SRO." The circular further required the SR0 to supervise core alterations which involved reactivity manipulations from the refuel deck. A review of these clarifications concluded in Reference (e) that (1) l
l Vermont Yankee's Technical Specifications do include the necessary provi-l sions (2) that station operating. procedures do contain the appropriate guidance relative to the operator's presence on the refuel floor, and (3) that VY has been correctly interpreting the regulatory requirements of reactivity mar.jpulations,
A more recent question arose regarding fuel assembly inspection in o the spent fuel pool. Typically, in this situation, an irradiated fuel assembly, is moved into a fuel prep machine where it is disassembled, inspected, or repaired.by a subcontractor. The movement of the fuel assembly into. or from, the prep machine is governed by AP 1000 and per-formed in the presence of a Senior Licensed Operator on the refueling floor. The disassembly, inspection, repair, or reassembly is governed by procedures written specifically for that task and is performed under the direction of the RE and Computer Supervisor, or his representative. e Interpritat164 Section 6 1.0.3. oL the Vermont, Yankee. Technical. Speci fication which ' reads, "ffVeen, sed Seafor Operator shall be in.chargerof any:refuelingf. ~ t opprestenFshalt be faterpreted to~meaab*a licensed Senior Operator. shalT /. . M NM.N5..fgi ggygsupeg1,sjng al1 comalteg - , _ . lh . s . . . ! MEMORANDUM
-/. :. , i . a. ... " ' } T0: J.P. Pelletiir " Vernon Maidh'18/1983' FROM: " ' '9.P. Kirphy ' ' Brattleboro FILE fi" ~ ~ ~ ' ' ' " ' . . ' l S.u.sJECT:
- *Riirii166'1'to Tich. Spei. Interpretation No. 28 - SR0 6n' Aef6il'F1666
.. .. . . . .
.
- ! 'l . '. . He may exercise indirect ': a :. '-) 2~ ,, .. . . i!T op ' ons but shall have no other ~ o r - - .. concurrent responsibilities." The licensed Senior Operator is not required to be present on the
- refuel floor during inspection of fuel pins which may be removed from the l
fuel assemblies secured in the fuel prep machines.
- J6itifidat166 Vermont Yankee Technical Specifications and Standard Technical
! Specifications require a licensed Senior Reactor Operator "be in charge ' of any refueling operation" a'nd that all core alterations be directly
s '. supervised by a licensed Senior Reactor Operator who has no other con-current responsibilities. Vermont Yankee's company policy as stated in AP '
i 1000, REFUELING, satisfies these requirements by requiring a licensed Senios - Reactor Operator to "be present on the refueling floor during movement of Irradiated fuel assemblies, and during any core alteration which involves a reactivity manipulation. References (a) and (d) simply provide further . i
definition and, justification regarding the Senior Reactor Operator'.s pre-sence, reactivity manipulations, and concurrent responsibilities. ...,. . [ ............ l ' warrfnP.Mur Vice Presiden d Manager of pe ons . { l - . '. ' o - WPM /dm cc: RJw - IJ85.4 ., RDP - . . 4-G . -- -- - -- --. . .- __ _ _ . _. . __ A ' - . 8z__eQdlNi@IB8IlVE_BBQGEQQBE@z_QQNQlligNSz_8NQ_biblI@IlgNS PAGE ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. ANSWER 8.01 (1.50) .The SRO is required E0.53 to be present as this is classified as an ALTERATION of the Rx Core.[1.OJ (1.50) M b ' REFERENCE VYNPC;T/S Def. ALT of Rx Core ANSWER 8.02 (2.00) Primary containment is NOT satisfactory.(0.75) The TIP valve is an automatic valve and it i s mal f unctioning. (0.5) ] Eitner of the following (0.75): 1. Restore the valve to OPERABLE status. 2. DEACTIVATE the TIP ball valve in the CLOSED cosition. (2.00) . REFERENCE i VYNPC: T/S Def. of Primary Containment Integrity ANSWER 8.03 (1.50) 1. t00 rem whole body (0.50) 2. 25 Rem whole body (0.50) 3. 12.5 Rem whole body (0.50) REFERENCE VYNPC: LOT-06 ~.05,Pg 11/12. Radi ation Fratetti cr. Etendares, SLO 1 , ANSWER S.04 (2.00) A. true C. false B. true D. true t.5 esch) (2.0) REFERENCE 10 CFR 50.72; VYNPC; A.P. 0156. LOT-06-301. Pg 55. ELC 26 -- . _. _ - _. _ _ _,. _ _, . . ... . -- , Ak . . Hz__0DdINISIB3IIVE_E8QgEQyBES1_CgNQlIlQN@i_9NQ_LIMII8IlQNS PAGE i ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. i e } ANSWER 8.05 (2.00) j_ l 1. It means that a licensed RO or SRO be in the area of the control room where he can see RMCS board.(see Figure II, A.P.OO36) (0.50) I 2. a) 1 SRO Shift Supervisor i b) 1 SRO Supervisory Control Room Operator / -2 RQmgControl Room Operator c) d) 2 Auxiliary Operators e) 1 Shift Engineer (.30 each) (1.50) REFERENCE VYNPC A.P 0036. SHIFT STAFFING, Figures I & II ANSWER S.06 (2.00) a) T5e Mode Switch must be locked in the REFUEL position /3.12.A ( 0.~ 50) b)'2 SRM's must be OPERABLE /3.12.B (0.50) c) S]$1 requirements must be satisfied /4.12.B d) All other (but one) Control Rods must be inserted /3.12.D (0.50) REFERENCE VYNPC: TS, 3.12 p, 9 g
- -
, ANSWER E.07 (1.50) , . '/e s (0.5'. A safety limit shall be assumed to be exceeded when a l scram is -:Complished by a means other than the expected scram ' s i g n s '. The scram should have occurred due to the MSIV
.. . 't.50) Valve ~;;; c. i REFERENCE ' !{ VYNFC Tec-cel Sper: f i c et i ons 3.1.A.B.C and 6.4
- s
' -t l { i f y -- , . . -.._: ,... -. _ _ _ _ -., - - - - -. -., _. _,,... -. _, - -, ... _.. AA ' - B___8DMINISIB@IIVE_EBQGEgyEES2_CQNpillgN@i_@ND_LIMlI@llgNS PAGE ' ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. I i ! ! !- ANSWER 8.# d (1.50) ! l NO.(.50) You must have Suporesion Pool water temp less than 100 degrees F before entering the Run Mode (.50) because Tech. Spec. i ! 3.7.A.1.c. does not permit power operation to be resumed until the suppression pool water temperature is less thatn 100 degrees F. ' i See TS definition of Reactor Power Operation.(.50) ( 1. 50) REFERENCE . VYNPC; Technical Specifications 3.7.A.1.c & definitions. ANSWER 8.09 (3.00) a) Potential loss of condenser vacuum, potential turbine building ' contamination. (1.00) . b) Investigate, and if plant conditions are deteriorating commence power reduction., secure Turbine Building roof ventilators and send operators with suitable protective clothing and radiation monitoring to check on the rupture disc in the SJAE room.Make (2.00) temporary repair. , P P - - , REFERENCE VYNPC: ON3151 Off Gas Explosion ' . ANSWER 8.)O (1.50) . a) In all situations of certain impending natural phenomens. consider l making arrangements to have the fuel oil storage tanks topoed-of f f 0. 50) , b1 Have Aun111ary Operators and Security Gaurds increase the frequency of their tours, reporting all unusual conditions to (0.50) the control room. c) Monitor plant instrumentation clossly and be preparea tc react to a loss of off-site power. (0.50) .I REFERENCE CP g Natural Disaster ! w.x .
_. - _ _ ._ _ _. - -,. _ _ . _..- _.,. _.... _. _, ., _ p
.. . a___eDMINi@IB8IIVE_E6QGEDUBE@t_GQND1IlgN@z_@ND_(ldlIGIlgN@ PAGE i
ANSWERS -- VERMONT, YANKEE-86/06/02-TURNER, R. tl . ANSWER 8.11 (2.00) a) The position agrees with the position stated in the appropriate , appendix of the governing procedure, as documented in the , . Current System Lineup Book , b) The position agrees with that required and controlled by a plant , operating or surveillance procedure. ~ . c) The position agrees.with that documented on a Lineup Deviation Form, per A.P. 0155. d) The component is tagged under another tagging order. (2.00) (two out of four for complete credit) REFERENCE VYNPC; A.P. 0140 Pg. 1 ANSWER 8.12 (2.50) a) Unusal event addresses potential problem with no radiactive release while an alert is more significant and involves an actual or potential sucstantial degradation of the level of the plant safety. (1.00) r b) Site energency involves failure of functions needed for the protection of the publec where the general emergency involves actual or imminent core degradation or meltir.g. (1.00)
c) When the Technical Support Center Coordinator assumes the ! rrsponsibility or you are relieved by the Site Recovery Nanager. (0.50)
i , REFERENCE
- 'Y NP C ; LOT-06-307. Intro to the Emerg. Plan, SLO 2
. C.F. 35^3. General Emergency. Appendix I. ! I 'r
! i (
- I
, . -... _., _ -. -.,, _. - . _. .-~. - .-._.._.,-...._.....,___.__-. _... _ _ __,_ __, _ _,_- - g . . az__eDMINigIg@Ilyg_e8QCEQUBESt_QQNQlIlQN$t_@NQ_LidlI@I1QNS PAGE ANSWERS -- VERMONT YANKEE-86/06/02-TURNER, R. ANSWER 8.13 (2.00) a)'The changes shall be documented and subsequently reviewed by the PORC and approved by the Plant Manager or his ' delegate. (1.00) b) Temporary changes to radiation control procedures may be made with the concurrence of an individual holding a SRO License and the HP on duty. (1.00) REFERENCE VYNPC; TS 6.5.D & E: Ad. Proc. not available. 4[OE31 _ i e f i
l. i, i l , l' , ( 3 . . _ - - - . - . . ~. ~ - - . \\ g $[d ., . . EQUATION 5HEET M ' i h = ma v = s/t Cycle efficiency = (Net work . out)/(Energy in) , = mg s = V t + 1/2 at' w E = mc? g . KE = 1/2 mv a = (Vf - V )/t A = AN
PE = mgn A=Ae
g Vf=V - at g
- = e/t A=
zn2/t 1/2 = 0.693/t 1/2 y,y 3p - A=n0 =l/2ef [(t )(t")] I
- .E = 931 m
[( Tp2). (t )} - m=V A3 av-nx . . I,ie Q = mCoat o . Q = UA T I = I e'"* Pwr = W ch f I=I 10-*/ M o P = P 10 d TVL = 1.3/u g .a = a o.t/T HR = -0.693/u . g SUR = 25.06/T SCR = 5/(1 - X,ff) CR = S/(1 - X - ' SUR = 25o / z* + ( 3 - a )T x efix> CR (1 - Keril) = CR (1 - k - i .. erf2' T = ( t"/o ) + [(3 - o /' Ic] M = 1/(1 - K T = 1/(p - 3) f.) = CR;/G 3 M = (1 - Kerro)/(1 - Keffl) T = (3 - 0)/(Io) .. SDid = II - K j er )/K . a = (Kgf,-l)/Kgff = 0.Kgff/K,ff .. eri t' = 10 seconcs
I = 0.1 secones'I = [(t*/(T Keff)] + 7,ff (1 + D o / l I o, = I d l P = (tav)/(3 x 1010) 2,2 2 j
I = 3N
- )d
- 2 2 d
! R/hr = (0.5 CE)/c (meters) R/hr = 5 CE/d2 gfggg) f Water Parameters Miscellaneous Conversions i 1 gal. = 8.345 lem. f Ig Ifja.=3.78 liters I curie = 3.7 x 10 10 ,. aps ! = 7.48 gal. 1 kg = 2.21 lom , . I Density = 52.4 lbqi/ft3 1np=2.54x103Stu/nr Density = 1 ga/c:r i av = 3.41 x 100 5tu/hr Heat of vaporization = 970 Stu/lom lin = 2.54 cm , Heat of fusion = la4 Stu/lbo
- F = 9/5'C + 32
1 Atm = 14.7 osi = 29.9 in. Hg.
- C = 5/9 (*F-32)
~ 1 ft. H O = 0.4335 lbf/in. I BTU = 778 ft-lbf i ' m c .. , .. . , _ > Table 1. Saturated Steam: Temperature Table .. _ _. _... . _... -.. _ . i Temp tb per Sat. Sal. S a t. Sat. Sat. Sat. Temp rahr sq in l irluid Ivap Vapor liquid Evap Vapor Liquid Evap Vapor Fahr i p vg vig. vg hg hgg h sg sig s I g r 12 0 0 08859 0 016022 33041 3304 7 0 0179 1075 5 1075.5 0.0000 2.1873 2.1873 32.0 34 I 0 09600 0 016021 3061 9 3061.9 1.996 1014 4 1076 4 0 004) 2.1762 21802 34.0 36 0 0 10395 0 016020 2839 0 2839 0 4.008 1073.2 1077.2 0 0081 2 1651 2.1732 36.0 38 0 0 11249 0 016019 26141 2634 2 6.018 10721 1078.1 0 0122 2.1541 2.1663 38.I 41 0 1.12163 0 016019 2445 8 2445 8 8.027 1071.0 1079 0 0 0162 2.1432 2.1594 40.0 47 0 0 13143 0 016019 2212 4 / 22724 10.035 1069 8 1079.9 0 0202 2.1325 2.1527 42.8 014192 0 016019 2112 8 2112 8 12.041 10681 1080 7 0 0242 21211 2 1459 44.s 44 0 . 46 0 0 15314 0036020 19651 19651 14.047 1067.6 1081.6 0 0282 2.11 l l 2.1393 48.9 40 0 0 16514 0 016021 in 10 0 1810 0 16 051 10664 1082.5 0 0321 2 1006 21327 48 9 50 0 0 17796 0 016023 1704 8 1704 8 18 054 10653 1083.4 0 0361 20901 2.1262 58.8 52 0 0 19165 0 016024 15892 1589 2 20 057 10642 1084.2 0 0400 2.0798 2.1197 52.0 54 0 0 20625 0 016026 1482 4 1482 4 22.058 1063.1 1085.1 0 0439 20695 2.1134 54 0 58 0 0 22183 0 016028 1383 6 1383.6 24.059 1061.9 1086.0 0 0478 2.0593 2.1070 58.8 58 0 0 23843 0 016011 1292 2 1292 2 26 060 1060 8 1086.9 0 0516 20491 2 1008 58 0 80 0 0 25611 0 016033 1207.6 1207 6 23060 1059 7 10873 0 0555 20391 20946 le e If I O21494 0 016036 1129 2 1129 2 30 059 1058 5 1088 6 0 0593 2 0291 2 0885 67 e 64 0 0 29491 0 016039 1056 5 1056 5 32.058 10514 1089 5 0 0632 20192 2OR24 64 e $5 0. 0 31626 0 016043 98'3 0 989 1 34 056 1056.3 1090 4 0 0670 2 0094 2.0764 58 I ElI O31889 0 016046 9265 926 5 36.054 1055 2 1091.2 0 0708 1.9996 2.0704 le I 10 8 0 36292 0 016050 868 3 868 4 38.052 1054.0 1092.1 0 0745 1.9900 2.0645 78.9 72 0 0 38844 0 016054 814 3 8i43 40 049 1052.9 1093 0 0.0783 1.9804 2 0587 72.8 14 0 0 41550 0 016058 7b41 1641 42 046 1051 8 1093.8 0 0821 19708 20529 74.0 76 0 0 44420 0 016063 117 4 7174 44 043 10507 10941 0 0858 1.9614 .2.04 72 76.9 IS O 0 41461 0016067 6)1R 673 9 46 040 1049.5 1095 6 0 0895 1 9520 2.0415 78.8 III O50683 0 016072 633 3 633 3 48.037 1048.4 1096.4 0 0932 1.9426 2.0959 88.8 12 I 054093 0 016011 595 5 595 5 50.033 10473 1091.3 0 0969 1.9334 2 0303 82.8 84.9 0 57102 0 016082 560 3 560 3 52 029 1046.1 1098 2 0.1006 1.9242 2 0248 84.0 Is t 0 61518 0 016081 221 5 521 5 54.026 1045.0 1099 0 0.1043 1.9151 2.0193 86.0 II I O65551 n nl609.1 496 8 4968 56 022 1043.9 1099 9 0 1079 1.9060 2.0139 II.O 90 0 0 69813 0 016099 468 1 4681 g 58 018 10427 1100.8 0 til5 1.8910 2.0086 99.9 97 0 0 74313 0 016105 441 3 441 3 60 014 1041 6 1101 6 0.1152 1.8881 2 0033 92.0 94 0 0 19062 0 016111 416 3 416 3 62 010 1040.5 1102 5 0 1888 1.8192 1.9980 94.I > 96 0 0 84012 0 016111 392 8 392 9 64 006 1039 3 1103.3 0 1224 1.8104 19928 95.0 ( 90 0 0 89156 0 016121 370 9 370 9 66 003 10382 1104 2 0 1260 1.8617 1.9876 98.0 . .e. <,+o
o o Y Aht Pseu Speratic Vnhame [nthalpy [ntropy ' '
Temp lb pe Sal Sol. Sat. Sat. Sal. Sat. Temp Iah Sq hi ihpihl I vap Vapor liquid Ivap Vapor liqunt Ivap Vapor Fahr i p vt V ig Vi hr h ig h g sg $gg g i s ,, _, 100 0 0 94924 0 016130 350 4 350 4 67.999 1037.1 11051 0.1295 1.8530 1.9825 tes.s 107 8 100789 0 016131 331 1 331 1 69 995 1035 9 1105 9 0 1331 18444 1.9775 182.8 104 I 106965 0 016144 313 1 313 1 11.992 1034 8 1106 8 0.1366 1.8358 1.9725 104.0 106 8 l1347 0 016151 296 16 296 18 73 99 1033 6 1101.6 0 1402 1.8273 19675 10s.3 los 0 I2030 0 016158 2802A 28030 15 98 1032.5 1108.5 0.1437 I8188 1.9626 148.8 lit I 1.2750 0 016165 265 37 265 39 77.98 1031.4 1109.3 0 1472 1.8105 19577 118.4 112 e 13505 0 016113 251 37 251 38 79.98 1030.2 1110 2 01507 I8021 1.9528 112.0 lit e I4299 0 016180 23821 238 22 81.97 10291 1111.0 0 1542 11938 1.9480 114.s Ils I I5133 0 016188 225 84 225 85 83.97 10279 1111.9 0 1577 17856 1.9433 115.8 IIII I6004 0 016196 214 70 f 214 21 85.97 1026 8 1112.7 0.1611 1.7714 1.9386 118.0 120 0 I6927 0016204 203 25 203 26 87.97 1025 6 1112.6 0 1646 1.7693 1.9339 126.0 122 8 17891 0 016213 192'34 192 95 89.96 1024 5 1114.4 0 1680 1.7613 1.9293 122.0 124 0 18901 0 016221 18323 18324 91 96 1023.3 til5 3 01 TIS 1.7533 1.9247 124.0 128 9 19959 0 016229 174 08 174 09 93.96 1022.2 1116.1 01749 1.7453 1.9202 120.0 IIII 2 1068 0 016?38 16545 16547 95.96 102).0 1117.0 01783 1.7374 1.9157 128.0 138.8 2 2230 0 016247 157 32 157 33 97.96 1019.8 1117.8 0.1817 1.7295 1.9112 130.0 132 0 2.3445 0 016256 149 64 14966 99 95 10187 1118.6 0.1851 1.7217 1.9068 132.0 134I 2 4111 0 016265 14240 142.41 101.95 1017.5 1119.5 0.1884 1.1140- 1.9024 134.9 136 8 2 6047 0 016274 135 55 135 57 103 95 1016 4 1120.3 0.1918 1.7063 1.8980 136.0 111 0 27438 0 016284 129 09 129 11 105.95 10152 1121.1 01951 16986 1.8937 130.0 140 0 't 8892 0 016293 122 98 123 00 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 144.0 142 I. 3 0411 0 016303 11121 11722 109 95 1012.9 1122.8 0 2018 1.6534 1.8852 142.0 144 I 3 1997 0 016312 1Ii 14 111 76 111.95 1011.7 1123.6 0.2051 1.6759 1.8810 144.8 149 0 3 3653 0 916322 106 58 106 59 113 95 1010.5 1124.5 0 2084 1.6684 1.8769 148.0 its e 3 MRI 0016312 101 68 101 10 115 95 1009.3 1125 3 0 2117 1.6610 1.8727 1 44.5 - 150 0 3 1184 0 016343 97 05 9707 117.95 10082 1126.1 0 2150 1.6536 1.8686' 154.4 152 8 3 9065 0 016353 92 06 9268 119.95 1007.0 1126.9 0 2183 1.6463.l.8646 152.0 1540 4 1025 0 016363 8850 8852 12195 51005 8 1127.7 02216 1 6390 1.8606 154.0 15E I 4 3068 0 016374 84 56 84 57 123 95 1004 6 1128 6 0 2248 16318 I.8566 156.0 15I I 4 5191 0016184 A0 8/ 810 83 125 96 1003.4 1129 4 0 2281 16245 1.8526 150.8 les I 4 1414 0 016395 7727 1729 127.96 1002.2 1130 2 0 2313 1.6174 1.8487 188.0 , l 162 8 4.9722 0 016406 7390 13 92 129 96 1001.0 1131 0 02345 1 6103 1.8448 182.0 164 8 52124 0016411 70 10 10 72 131.96 999 8 1131.8 0 2377 1.6032 1.8409 134.0 III I 54623 0 016428 6767 6768 133 97 998.6 1132.6 0 2409 1.5%I 1.8371 180.8 Ils I 5 7223 0 016440 64 1S 64 80 13597 997.4 1133.4 02441 1.5892 1.8333 164.0 IIII 5 9926 0 016451 62 04 6206 137.97 996.2 1134.2 0 2473 1.5822 1.8295 17t.8 1128 6 2136 0016463 59 43 59 45 139.98 995.0 1135 0 0 2505 15753 1.8258 172.0 174 0 6 5656 0 016414 56 95 56 97 141.98 993 8 1135.8 0 2537 1.5644 1.8221 174.s ~ III I 6 8690 0 016486 54 59 54 61 143.99 992.6 1136 6 0 2568 1.5616 1.8184 178.0 178 8 71840 0 016498 52 35 52 36 14599 9914 1137.4 0 2600 1 5548 1 8147 178.8 . - ' g3 . _- . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ _ _. _ _ _ _ _ .: - r. Abs Pren - Specihc Volurne Enthalpy Entropy ,' Temp lb per Sat Sat Sal Sat. Sal Sat Temp Iatir Sq in Iiquut [vap Vapor liquid Evan Vapor liquid Ivan Vapor Fahr i p V (ep vp he h ig h 5, 5,g s i g g 100 0 15110 0 016510 50 21 50 22 14800 990 2 1138.2 02631 1.5480 18111 188.4 102.I 7850 ' 0 016522 48 112 18 169 150 01 989 0 1139 0 0 2662 1.5413 18075 182.0 184 8 8 203 0 016534 4G 232 46 249 152 01 987.8 1139 8 0 2694 15346 18040 1 84.0 lesI 8.568 0 016547 44 383 44 400 154 02 986 5 1140 5 0 2725 15219 1.8004 IIE.8 tes e 8 941 0 016559 42 67I 42 638 156 03 985 3 1141.3 02756 1.5213 13%9 118.0 leg g 9 340 0 016512 40 94 [ 40 957 158 04 984.1 1142.1 0 2787 1.5148 IJ934 IM.O 132 9 9347 0 016585 39 331 39 354 160 05 982.8 1142.9 0 2818 1.5082 13900 192.5 194.0 10.168 0 016598 37 808 37824 162 05 981.6 11433 0'.2848 1.5017 13865 184.0 198.0 10 605 0 016611 36 348 36 364 164 06 980.4 1144.4 0.2879 1.4952 1.7831 196.8 198.3 11 058 0 016624 34 954 34 970 166 08 979.1 1145.2 0.2910 1.4888 13798 198.0 260 I 11 526 0016637 33 622 33 639 168 09 977.9 1146.0 0 2940 1.4824 13764 208.8 294 8 12 512 0 016664 31 135 31151 172.11 975.4 !!47.5 0 3001 1.4697 13698 204.8 288 8 13 568 0 016691 28 862 28 818 176 14 9 72.8 1149 0 0.3061 1.4571 1.7632 298.8 212 I 14 696 0 016/19 26 162 26 199 18011 910.3 1150.5 0.3121 1.4447 1.7568 212.0 216 0 15 901 0 016141 24 R18 24 894 184 20 9678 1152.0 0 3181 1.4323 13505 216.8 220 0 17.186 0 016715 23 131 23 148 188 23 965.2 1153.4 03241 14201 1.7442' 229.8 ' 224.0 18 556 0 016805 21 529 21 545 192 27 962.6 1154.9 0.3300 1.4081 13380 224.0 228 0 20 015 0 016834 20 05G 20 073 196 31 960 0 1156.3 0 3359 1 3961 13320
- 228.9 232.0 21561 0 016864 18 701 18 118 20035 957.4 1157.8 0 3417 13842 13260 232.0 236 I 23 216 0 016895 17 454 11 411 204 40 954 8 1159.2 0 3416 13725 1.1201 225.I 240 0 24 968 0 016926 18 304 16 321 208 45 952.1
!!60.6 0 3533 1.3609 17142 248.9 244s 26 826 0 016958 15 243 15 260 212.50 949.5 1162.0 0.3591 1.3494 13085 2448 241 0 28 196 0 016990 14 264 14 281 216.56 946.8 1163.4 0 3649 1.3379A IJ028 248.9 252 0 30 883 0 01/0/2 13 358 13 315 220 62 944.1 !!643 0 3706 1.3266 16972 252.s 258 e 31 091 0 01/055 17 570 12 538 224 69 941.4 11661 0 3763 1.3154 16917 255.0 200 0 35 427 0 011089 11 745 !!]62 22836 938 6 1167.4 0.3819 1.3043 16862 250.5 284 8 37.894 0 01/123 11.025 11 042 232 83 935 9 11683 0 3816 12933 16808 254.0 288 8 40 500 0 01/151 10 358 10 315 236 91 933I 1170 0 0 3932 12823 16755 250.0 212.0 43 249 0 011193 9 138 9 755 240 99 930 3 1171 3 0 3987 12115 16702 272.0 218 8 46 141 0 0172?8 9 162 9 IE0 245 08 921 5 1112 5 04043 12601 16650 276 8 200 8 49 200 0 017264 R 627 8 644 24917 924 6 1173 8 04098 12501 16599 289.9 284 0 52 414 0.01130 8 1780 8.1453 2533' 9217 1175 0 04154 12395 1 6548 284.8 200 I 55795 0 01734 7 6634 7 6807 2514 918 8 1176 2 0 4208 12290 16498 288 9 292.0 59 350 0 01738 12301 72415 2615 915 9 l l 71.4 0 4263 1.2186 1 6449 292.8 296 O 63 084-0 01141 6 R759 6 R413 265 6 913 0 1178 6 04317 1.2082 16400 296.8 . _ _ _ _ _ - _ _ _ _ _ _ _ _ _.. - - - _ _ _ _ _ _ Y . I c, . Abs Press. Sper.ific Volume Enthalpy Entropy Temp Lb per Sal Sat. Sat. Sa t. Sat. Sat. Temp fahr Sq in liquial Evan vapor Li vid Evap Vapor Liquid Evap Vapor Fahr I p V 3ee I ~'5T0057 _ L Vit Vs I h rg h g s, sgg g ( s 0 01145 6 4483 6 4658 269.7 910 0 1179.7 0 4372 1.1979 I6351 300 s 3M I ' 71 129' 001149 6 0955 6 !!30 273 8 907.0 1180 9 0 4426 1.1877 16303 364 e 398 8 75 433 0 01153 5 1655 5 1830 278 0 904 0 1182 0 04419 1.1176 1.6256 308.8 312 0 79 953 0 01157 5 4566 54/42 2821 901.0 1183.1 04533 'l.1676 16209 312.0 31s e 84 688 0 01161 5 1613 51849 286 3 891.9 1184.1 0 4586 1.1576 1616: 31E.e 329 8 89 643 0 01766 4 8961 4 9138 290 4 894 8 1l85 2 04640 1.1477 1.6116 320.0 324 8 94 826 0 01110 4 6418 4 6595 294 6 891.6 1186 2 04692 1.1318 I6071 324.0 320 0 100 245 0 01174 4 4030 4 4208 298 7 888 5 1187 2 0 4745 1.1280 1.6025 370 0 j 332 0 105 901 0 01/19 4 1788 4 1966 302 9 885 3 1188 2 0 4798 1.1183 1.5981 333.0 334 I Ill 870 0 01183 3.96R I 39859 301.1 882.1 11891 0 4850 1.1086 1.5936 336 I . 340 8 117.992 0 01181 3 7699 3 7878 311 3 878 8 11901 04902 10990 15892 348.9 344 I 124 430 0 01192 3 5834 3 6013 315 5 875 5 !!91 0 0 4954 10894 15849 344.8 348 8 131.142, 0 01191 34018 3 4258 319 7 872 2 1191.1 0 5006 10799 15806 348 8 352 8 138 138 0 01801 3 2423 3 2003 323 9 868 9 !!921 0 5058 10705 15763 352.0 35s e 145 424 0 0lR06 3OR63 3iM4 328I 865i 1193 6 0 5110 10611 15121 356 e 364 I 153.010 0 01811 29392 29573 332 3 862 I 1l94 4 0 5161 10517 1.5678 364 8 364 8 160 903 0 01816 2 8002 2 8184 336 5 858.6 1895.2 0 5212 1 0424 1.5637 354.s 388 I 169 113 001821 26691 2 6813 340 8 855.1 1l95 9 0 5263 10332 1.5595 368.8 372 0 171 648 0 01826 2 5451 2 5633 345 0 8516 1196 1 0 5314 1 0240 1 5554 372.s 378 8 186 511 0 01 R 31 2 4219 24467 349 3 84RI 1197 4 0 5365 1.0148 1,5513 315.8 380 I 195 129 0 01836 2 3110 2 3353 353 6 844 5 1l98 0 0.5416 10057 1.54 73 388.9 354 8 205 294 0 01842 ??l20 2 2304 3519 8408 1198 7 0 5466 0 9966 1.5432 3 84.s lit 8 215 220 0 01841 2 1126 2 1311 362.2 837 2 1199 3 0.5516 0.9816 1.5392 318.0 392 0 225 516 0 01853 2 0184 2 0369 366.5 833 4 1199 9 0 5567 0.9186 1.5352 392.0 30s e 236193 0n1R58 I929' I9417 310 8 8297 1200 4 0 5617 0 9696 1,5313 396.0 400 8 247259 0 01864 18444 iP630 315 1 825 9 1201.0 0 5667 09607 1.5274 400 0 404 0 258 125 0 01870 11640 11821 379 4 822 0 1201.5 0 5717 0 9518 1.5234 404.s 400 I 270 600 0 01815 16811 1 1064 3818 818 2 1201.9 0 5766 0 9429 1.5195 40s e ' 412 0 282 894 0 01881 16152 1 6340 388 1 814.2 1202.4 0.5816 0 9341 1.5157 412.8 4III 295 617 00lRR7 1 5461 1 % 51 392 5 810 2 1202.8 0 5866 09253 1.5118 416 8 420 I 308 780 0 01894 14808 14997 396 9 806 2 1203.1 0 5915 0 9165 1.5080 428 8 424I 322 391 0 01900 14184 14314 401.3 802 2 12015 0 5964 0.9077 1.5042 424.0 428 0 336 463 0 01906 13591 13182 405 7 1980 12037 0 6014 0 8990 15004 428 8 437 0 351 00 0 01913 130266 1 32119 410 1 193 9 1204 0 0 6063 0 8903 1.4966 432 e all 0 366 03 001919 124RR1 126R06 dia6 1891 12N 2 0 6112 0 8816 14928 435 8 440 0 381 54 0 01926 119161 121651 419 0 785 4 1204 4 0 6161 0 8729 1.4890 440 0 ^ 4440 397 56 0 01933 114814 116806 423 5 781 1 1204 6 0 6210 0 8643 14853 444s 444 0 414 09 0 01940 110712 1!?!52 428 0 716 7 1204.7 06259 0 8557 1.4815 448 I g-***I 431 14 0 01941 105164 101111 ~ 12 5 112 3 1204 8 0 6308 0 8411 14778 /.qt . . .I 448 13 0 01954 101518 103412 J1.0 161 8 1204 8 06356 0 8385 1.4141 W4e - . ,p - . s. Aln l'ress ~ Specifer Volume [nthalpy Entropy Temp lb per Sal Sal Sal. Sal. Sal Sat. Temp Iahi Sqin l erpurl Fvap Vapor I. squid [ van Vapor liquid Evap Vapor Fahr i p vg V ig_ vg hr hit h s, 5,g g g I 468 8 466 87 001961 0 97463 0 99424 441.5 7612 1204 8 0 6405 08299 1.4704 44e.9 464 0 485 56 0 01969 0 93588 0 95557 44 6.1 758 6 1204.7 0 6454 0 8213 1.4667 464.s 468 8 504 83 0 01976 0 A9885 0 91862 4507 754.0 1204.6 0.6502 0 8127 1.4629 468.8 472 8 524 67 0 019R4 0 86345 0 88329 455 2 7493 1204.5 0.6551 0 8042 1.4592 472.0 dis e 545 11 0 01 % 7 0 8/95R OR4950, 459.9 744 5 1204.3 0 6599 0.7956 1.4555 476.8 4I00 566 15 0 02000 0 19116 / 0 81711, 464.5 739 6 1204.1 0 6648 0.7871 1.4518 40s.O 414 8 587 81 0 02009 016613 0 18622 * 469 1 '734.7 1203.8 06696 0.7785 1.4481 484.9 ' 411 0 610 10 007011 0 13641 01565R 473 8 729.7 1203.5 0.6745 0.7700 1.44 44 488.9 492 8 633 03 0 02026 0 10191 0 12820 418 5 724 6 1203.1 0 6793 0 7614 1.4407 492.0 496 0 6 % 61 007014 06R06', 010100 4832 719 5 1202.7 06842 0 7528 1.4370 496.0 500 I 680 86 0 02043 0 65448 0 67492 487.9 714.3 1202 2 0.6890 0.7443 1.4333 500.9 504 0 10538 0 07053 042938 0 64991 492.7 709.0 1201.7 0.6939 0 7357 1.42 % 584.0 501 I 731 40 0 02062 0 60530 0 62592 497.5 7037 1201.1 0 6987 0.7271 1.4258 50s.s . 512 0 75172 0 02012 058218 060289 502.3 698 2 1200.5 0.7036 03185 1.4221 512.s 518 0 1R416 0n7081 0 'M1 0 58019 5071 692 7 1199.8 0 7085 0 7099 1.4183 516.0 521 8 812 53 0 02091 0 53864 0 55956 512.0 687 0 1199 0 0 7133 03013 1 4146 529.9 574 8 841 04 0 02102 0 51814 0 53916 516 9 681.3 1198.2 0.7182 0 6926 1.4108 524.0 578 9 810 31 0 02112 0 49843 0 51955 521 8 615 5 1197.3 0 7231 0 6839 1.4010 528 8 532 8 900 34 0 02123 0 41947 0 50070 5268 669 6 1196 4 0 7280 0 6152 1.4032 532.9 536 8 931.17 0 02134 0 46173 048?S1 531.7 663 6 1195.4 0 7329 0 6665 1.3993 536.0 548 8 962 79 0 0?!46 (144361 0 46513 536 8 657.5 1194.3 0 7378 0 6577 1.3954 549.9 , 544 I 995 22 0 02157 0 42611 0 44834 541 8 651.3 1193.1 0.7427 0.6489 1.3915 544.8 540 0 1028 49 0 02169 0 41048 0 43217 546 9 645 0 1191.9 0 7476 0.6400 1.3876 548.e 552 0 1062 59 0 02182 0 39479 0 41660 552 0 638.5 1190.6 0 7525 0 6311 1.3837 552.s 556 I 1097 55 0 07194 0 11966 040160 5572 632.0 1189 2 0 1575 0 6222 13797 556.9 500 I 1133 38 0 02207 0 36507 0 38714 562.4 625 3 1187.7 0 7625 0 6132 13757 564 8 584 0 1170 10 002221 0 35099 0 31320 567.6 618.5 1186.1 0.7674 0 6041 1.3716 564.s $50.0 1201 12 0 02235 0 33141 0 35975 572 9 611.5 1184.5 07725 0 5950 1.3675 568.0 572.0 1246 26 0 02249 0 32429 0 34678 578 3 604.5 l182.7 0 7715 0 5859 1.3634 572.s 578.8 1285 74 0 02764 0 31162 0 33426 583 7 597.2 1180.9 07825 0 5166 1.3592 578.0 $48.0 1326 17 0 02279 0 29931 0 32216 589.1 589.9 1179 0 0 7876 0 5673 1.3550 580.0 584 0 1367 7 0 02295 0 28153 0 31048 594.6 582 4 1176 9 0 1927 0 5580 13507 584.0 588.0 1410 0 0 02311 0 27608 0 29919 6001 5743 1l74 8 0 1978 05485 1.3464 588.0 Y 592.0 1453 3 0 02328 0 26199 0 28827 6051 566 8 1872.6 0 8030 0 5390 1.3420 592.8 ". 508 I 14918 0 07345 075425 0 21770 611.4 558.8 1170.2 0 8082 0 5293 13375 598.8 . - _ __ __ - ________ _ ___ _ _ _ _ - _ .. , m a ~ ~~ '~ Specific Volume . Enthalpy Entropy Ahs I' vets temp lb per Sal. Sal. Sal. Sal. Sal. Sal. Temp ' fahi Sqin liquid Fvap Vapct ll uid Evap Vapor liquid Evap Vapor Fahr I P V f V ig_ _ i f h ig h V g s, sgg 5, g 800 8 15432 0 02364 0 24384 0 26747 617.1 550 6 1167.7 0.8134 0.5196 1.3330 840.9 844 I 1589 7 0 02382 0 23314 0 25757 622.9 542.2 1165.1-0.8187 0.5097 1.3284 644.0 Ist s 16373 0 02402 0 22394 0 24796 628.8 533.6 1162.4 0.8240 0 4997 1.3238 648.0 112 8 1686.1 0 02422 0 21442 0 23865 634.8 524.7 1159.5 0 8294 0.4896 1.3190 $12.0 EIII 1135 9 0 07444 0 70516 0 72960 640 8 515.6 1156.4 0.8348, 0.4794 1.3141 lis.t 0 1961 ! 0 22081 520 I s !786.9 0 02466 646.9 506.3 1153.2 0.8403 0.4689 1.3092 829.0 824 s 1839 0 0 02489 0 18737 0 21226 653.1 4?6.6 1149.8 0 8458 04583 1.3041 824.s $2s e 18924 0 02514 011880 0 20394 659.5 486.7 1146.1 0 8514 0 4414 1.2988 828.8 832 8 1947 0 0 02539 011044 0.19583 665.9 476.4 1142.2 0.8571 0 4364 1.2934 632.9 838 8 20078 0 07566 0 16126 0 18197 612.4 465 7 1138.1 0 8628 0 4251 1.2879 634.0 840 0 2059 9 0 02595 0 15421 0 18021 679.1 454.6 1133.7 0 8686 0 4134 1.2821 640.8 844 8 2118 3 0 02625 0 14644 0 11269 685 9 443.1 1129.0 0 8146 04015 1.2761 644.0 548 I 2118 1 0 02651 0 13816 0 16534 632.9 431.1 1124.0 0 8806 0 3893 1.2699 648.8 852 0 2239 2 0 02691 0 13124 0.15816 700 0 418 7 11187 0 8868 0 3767 1.2634 652.0 - 858.8 23011 0 07178 0 I?lR1 0 15115 707.4 405 7 1113.1 0 8931 03631 1.2567 SH.e 880.3 2365 7 0 02768 0 11663 0 14431 714.9 392.1 1107.0 0.8995 0 3502 1.2498 980.0 , 464 0 2431.1 0 02811 0 10941 0 13757 722.9 377.7 1100.6 0 9064 0 3361 1.2425 664.4 ' lit 8 24981 0 02858 0 10229 0 13087 731.5 362.1 1093 5 0.9137 0 3210 1.2347 668.e 872.0 2566 6 0 02911 0 09514 0 12424 740 2 345.7 1085.9 0.9212 0.3054 1.2266 672.0 Ill t 2636R 0 02910 0 08199 0 11169 749 2 328.5 1071.6 0.9287 0.2892 1.2179 878.0 000.0 2708 6 0 03037 0 08080 0 till7 758.5 310.1 1068.5 0.9365 0.2720 1.2086 ~ 888.4 884.0 27821 0 03114 0 01349 0 10463 763 2 290.2 1058.4 0.9447 0.2537,. 1.1984 644.0 III s 28574 0 03704 0 06595 0 09799 778.8 268.2 1047.0 0 9535 02337 1.1872 888.0 802.8 2934.5 0 03313 0 05797 0 09110 790.5 243.1 1033.6 0. % 34 0 2110 1.1744 592.8 898.8 3013.4 0 03455 0 049I6 0 08371 804.4 212.8 1017.2 0 9749 0.1841 1.1591 6M.0 70s.9 3094.3 0 03662 0 03857 0 07519 822.4 172.7 995.2 0.9901 0.1490 1.1390 700.0 702.0 3135.5 0 03824 0 03173 0 06991 835.0 1441 979.7 1.0006 0 1246 1.1252 762.0 164.0 3177.2 0 04108 0 02192 0 06300 854.2 102.0 956.2 1.0169 0.0816 1.1046 794.0 70s g 3198 3 0 04427 0 01304 0 05730 873 0 61.4 934.4 1.0329 0.05?? 1.0856 705.0. 79547* 37082 0 0507R 0 00000 0.05078 906.0 0.0 906.0 1.0612 0 0000 1.0612 705.47' . ! ' Critical temperature ] ' , ,
- ..
) . . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . Table 2: Saturated Steam: Pressure Table ' Abs Press. Temp Sal Sat. Sat. Sat. Sat. Sat. . Abs Press. , l lblSO in Fahr liquid Ivan Vapor Lic uid Evap Vapor liquid Evap Vapor Lb/Sq In. p I vi v, t v i f hg h s, sf2 'P i g g 180865 32 018 0 0160 2 3302 4 0.0003 1075 5 1075.5 0 0000 2.1872 2.1872 0.98885 0 25 59 323 0 016032 1235 5 1235 5 27.382 1060 1 1087.4 0 0542 2 0425 2.0967 8.25 , l 8 58 19 586 0 016011 641 5 641.5 41.623 1048.6 1096.3 0 0925 1.9446 2.0370 8.54 II 101 14 0 016136 331 59 333.60 6973 10361 1105.8 0.1326 1.8455 1.9781 1.s SI 162 24 0 016401 13 515 13 532 130.20 1000 9 1131.1 0 2349 1.6094 1.8443 III 193 21 0016592 38404 38420 161.26 9821 1143.3 0.2836 1.5043 1.7879 10.8 14 $$1 212 00 0 016719 26 182 /26 199 180.17 970 3 11505 0 3121 1.4447 1.1568 14.698 15 8, 213 03 0016176 76 714 76 290 131.21 9691 1150.9 0.3137 1.4415 1.7552 15.0 20 0 227 96 0016834 20 010 20 087 196 27 9601 1156.3 0.3358 1.3%2 1.7320 29.9 30 0 25034 0 011009 13 1766 13 1436 218.9 945 2 1164.1 0.3682 1.3313 1.6995 38.9 40 e 26725 0011151 10 4794 10 4965 236I 933 6 1169 8 0.3921 1.2844 1.6765 48.8 SO I 281 02 0 011274 8 4967 8 5140 2502 923 9 !!74.1 0.4112 1.2474 1.6586 58.8 80 8 29211 0 011383 11562 7 1736 262.2 915 4 1177.6 0.4273 1.2167 1.6440 se s Te e 302 93 0 017482 6 1875 6 2050 272.7 901.8 1180.6 0 4411 1.1905 1.6316 78.8 00 0 312 04 0 011513 5 4536 5 4111 282.1 900.9 1183.1 0 4534 1.16M 1.6208 80.0 se e 320 28 0 011659 4 8719 4 8953 290 7 894 6 1185.3 0.4643 1.1470 1.6113 19.9 100 0 32782 0 017140 4 4133 4 4310 298.5 888 6 1187.2 0 4743 1.1284 1.6027 188.9 110 0 334 19 001187 4 0306 4 0484 305 8 883.1 Il88 9 0 4834 1.1115 1.5950 110.8 12e e 341 21 0 01189 3 1091 3 1215 312.6 877 8 1190 4 0 4919 10960 1.5819 120 0 130 8 34733 0 01196 3 4364 3 4544 319 0 812 8 1191.7 0 4998 1 0815 15813 13e 8 140 s 353 04 0 01803 3 2010 3 2190 325 0 868 0 1193.0 0 5071 1.0681 1 5752 148.0 1500 358 43 001809 29958 30139 330 6 863 4 1194.1 0 5141 10554 15695 158 I 160 0 363 55 0 01815 ?8155 2 8336 3361 859 0 1195 1 0 5206 1.0435 I5641 Ils I 110 0 368 42 0 01821 2 6556 26138 3412 854 8 1196.0 0 5269 10322 1.5591 lit I 140 t 313 08 0 01821 2 5129 25312 346 2 850 7 1196.9 0 5328 10215 i 1.5543 184.0 les e 37753 0 0l R 11 ? 3841 2 4030 350 9 8461 1197.6 0 5384 iOll3 15498 Ile t 20e 1 38180 001819 ?2689 2 2813 355 5 847 8 1198 3 0 5438 10016 I 54 54 200 8 110 e 385 91 0 01844 216313 218?ll 359 9 8391 l199 0 0 5490 0 9923 15413 218 O 220 8 389 88 001850 2 06119 2 08629 3642 835 4 l199 6 0 5540 0 9834 15314 228 e 210 I 393 10 0 01855 l91991 199846 368 3 831 8 12001 0 5588 0 9148 15336 23e e 240 0 397 39 0 01860 189909 191169 312 3 828 4 1200.6 0 5634 0 9665 15299 240.0 2500 400 91 0 01865 1 82452 1.84317 376.1 825 0 1201.1 0 5679 0 9585 1 5264 250 0 260 8 404 44 0 01810 115548 171418 379 9 821 6 1201 5 0 5122 0 9508 1.5230 268.0 fie I 40780 0 01815 169131 111013 383 6 818 3 1201.9 0 5164 0 9433 15197 270 0 > 200 0 411 01 0 01880 163169 I65049 381.1 815 1 1202 3 0 5805 0 9361 1.5166 240 0 & 299 0 414 75 001885 I51591 15948? 390 6 812 0 1202.6 0 5844 0 9291 1.5135 298 e 300 3 41735 0 01889 152384 154274 394.0 808.9 1202.9 0 5882 0 9223 1.5105 300.0 . 350 0 431.13 0 01912 130642 1.32554 409 8 194 2 1204.0 0 6059 0 8909 1.4968 358.8 400 0 444 60 0 01914 1~.6? I16095 424.2 780 4 1204.6 0 6217 0 8630 1.4841 400 e .
" . " Ab5 Prest Temp Sal Sal. Sal. Sal. Sal. Sal. Abs Press. , l' Ih/Sq in Fahr I ispiiel ivap Vapor liquid Ivap Vapor liquid Evap Vapor lb/Sg in. .
- $
p i vb h h S S V, h i ig g g Sgg g p V 4500 456 78 0 01954 101224 103119 4313 167 5 1204.8 06360 0.8378 1.4138 450 0 500 0 461 01 0 01915 0 90181 0 92162 449.5 7551 1204 7 0 6490 0 8148 1 4639 5000 550 0 416 94 0 01994 0 8/181 0 84111 460 9 143 3 1204.3 0 6611 0 1936 14547 550 0 600 0 486 20 0 02013 0 14967 0 16915 471 1 732 0 12031 0 6723 0 7738 14461 600 0 650 0 494 89 0 07032 0 68811 0 10843 481.9I 720 9 1202.8 0 6828 0 1552 1 4381 650.8 700 0 503 08 0 07050 0 63505 0 65556 4916 710 2 1201 8 0 6928 0.7377 14304 700.1 758 I 510 84 0 07069 0 58880 0 60949 500 9 639 8 1200 7 0 7022 0 7210 1.4232 158.8 800 0 518 21 0 0/081 0 54809 0 56896 509 8 689 6 1199 4 0.7111 0 7051 14163 800.8 858 I 525 24 002105 0 51191 0 53302 518.4 619 5 1198 0 0.7197 0 6899 1.4096 150 8 900 0 53195 0 0?!?) 041968 0 50091 526 7 669 7 1196 4 0 1279 0 6753 1.4032 900.0 950 0 538 39 0 0/141 0 45064 0 41205 5347 660 0 1194.7 0.1358 0 6612 1.3970 150.8 10000 544 58 0 0?!59 0 42436 0,44596 542 6 650 4 1192.9 0 7434 0 6476 1.3910 10000 1850 0 550 53 0 02111 0 40041 0 42224 5501 640.9 1191.0 0 1507 0 6344 1.3851 1950.8 1100I 556 28 0 02195 0 31863 040058 557.5 631 5 1189.1 0 1578 0 5216 1.3794 1100.0 ' 11500 561 82 0 02214 0 35859 0 38073 564 8 6?22 1187.0 0.7647 0 6091 13738 1150.0 120s 8 56719 0 0??17 0 34011 0 36245 571.9 613 0 1184 8 0.7714 0 5969 13683 1200.0 12500 572 38 0 02250 0 37306 0 34556 578 8 603 8 1182 6 0 1780 0 5850 13630 1758 I 1300 0 51142 00??69 0 30122 0 3?991 585 6 594 6 1180 2 0 7843 0 5133 13511 13000 1350 0 582 32 0 07/88 0 29250 0 31531 592 3 585 4 till8 0 7906 0 56?0 1.3525 13500 1400 0 581 01 0 0/101 0 21811 0301/8 598 8 516 5 1175.3 0 7966 0 5501 1 3414 14005 1450 0 591 10 0 02321 0 76584 028911 605 3 5674 1172 8 0 8026 0 5391 13423 14500 1500 0 595 20 0 02346 0 25312 0 21119 611 7 558 4 11701 0 8085 '05288 13313 1500.8 1550 0 600 59 0 0?366 0 24?35 0 26601 618 0 549 4 11674 0 8142 0 5182 13324 15500 1600 0 604 87 0 0/181 0?3159 025545 624 2 5403 1164.5 0 8199 0 5016 13214 16000 1650 0 609 05 002401 0 ??l43 0 24551 630 4 531 1 11616 0 8254 0 4911 13??5 .1650 0 1700 0 61113 0 0742R 02111R 021601 6.16 5 522 2 1158 6 0 8309 0 4861 13I16 Iice I Ilse e 611.12 0 02450 0 20283 0 22713 642.5 513 1 1855 6 0 8363 04165 1.3128 1750 e 1800 0 82102 0 024/2 0 19390 0 21261 648 5 503 8 1152 3 0 8417 0 4662 13019 1100.0 1850 0 624 83 0 02495 0 18558 0 21052 654 5 494 6 1149 0 0 8470 0 4561 1.3030 18500 1900 0 628 56 0 02511 011161 0 70218 650.4 485.2 1145.6 0 8522 0 4459 1.2981 1900 e 1950 8 632 22 0 02541 0 16999 0 19540 666 3 415 8 1142.0 0 8574 0 4358 / 1.2931 1950I 2000 0 635 80 0 07565 0 16266 0 18831 672.1 466 2 1138 3 0 8625 0 4256 12881 2000I 2I00 0 642 16 0 01615 0 14885 0 11501 683 8 446 7 IJ 30 5 0 8721 0 4053 12180 2l00e ' ' 22000 64945 002669 0 13603 0 16?/2 695 5 4267 1122 2 0 8878 0 3848 12616 2200.0 23000 655 89 00/1/1 0 12406 0 15133 107 2 406 0 til3 2 0 8929 0 3640 12569 23000 2400 0 662 11 00/190 0ll/R1 0 14016 119 0 3R4 8 11031 0 9011 0 3430 12460 fees e 25008 668 11 0 02859 0 10709 0 13068 131.7 361 6 1093 3 0 9139 0 3?06 12345 2588 9 2I00 0 613 91 0 02938 0 091/2 O l?ll0 144 5 3316 10820 0 9241 0 2971 1.2225 26000 21000 679 53 0 03079 0 08165 0ll194 151 3 317 3 10697 0 9356 0 2141 1.2091 27000 - 2800 0 684 96 0 031.14 0 01111 0 10305 1101 285l 1055.8 0 9468 0 249l 1.1958 2800.9 29008 690 22 0 03762 0 06158 0 09420 7851 2541 1039 8 0 9588 0 2215 1.1803 2900.0 3000 0 695 33 00J428 0 05013 0 08500 801.8 218 4 1020 3 0 9728 0 1891 1.1619 300s.e 3l000 10028 0 016HI 003/11 0 01452 824 0 169 3 993 3 0 9914 01460 1.1373 3100.0 32000 705 08 0 044/? 001191 0 05663 815 5 56 I 931.6 10351 0 0482 1.0832 320e 8 3701 2-705 41 0 0'.01R 000000 0 05018 906 0 906 0 10612 0 0000 1.0612 3298.2* f . . . Q" .
- Crs..J al nressure
.- _ _ _ _ _ _ - _ -. _ _ _ _ _ _ _ _ _ . ' f:: f .,. = ( , x - . , ! . ! ' . ..,6 ! . . . e .. t e - , l - . ,
- f APPENDIX A
- , . . - '1D i - . i OPERATING LICENSE DPR-28 g . . TECHNICAL SPECIFICATIONS . . AND BASES
FOR. . g VERMONT YANKEE NdCLEAR POWER STATION VEREON, VERMONT . . VERMONT YANKEE NUCLEAR POWER CORPORATION EOCKET NO. 50-271 . - . _ . . Reissued by ,,.,,, Changes Nos.13,15 and 17 D:tsd 1/17/74,1/28/74, and 4/10/74 . . $
. . - , . e r . . , - . ..f
.
. , . l TABLE OF CDNTENTS Fore No. . . . ' CENERAL . - - - - - - - - - - - - - - - - - - - - - - 1.0 DEFINITIONS ' i - - - - - - - - - - - - - - - - - - - - - - - 188 s - - - - , S.O DESIGN FEATURES 190 - - - - - - - - - - - - - - - - - - - - - 6.0 ADMINISTRATIVE CONTROLS - - ' ' 190 4.1 ORCANIZATION -- - - - - - - - - - - - - - - -. - - 194 - - - - - - - - - - - - - - - - - - - - - - - l6.1 REVIDI AND AUDIT --- 194 - - - - - - - i Plant Operation Review comunittee --------
196 1.
A.
Nuclear Saf ety Audit and Review caamalttee -
j B.
.
I ACTION TO BE TAKEN IN THE EVENT OF AN ABNORMAL
-
199 l 4.3
---
OCCURRENCE IN FLANT OPERATION -----------~~-- -
199 ACTION TO BE TAKEN IF A SAFETT' LIMIT IS EXCEEDED --
-----
!
200 l 6.6
- - - - - - - - - - - - -
- - - - - - - - -
l 6.5 FIANT OPERATINC PROCEDUKES
- - - - - - - - - - -
- - - - - - - - - - - - - -
207 FLANT OPERATINC RECORDS -- - -
208 i
6.6 FLANT REPORTING REQUIRDENTS -- ----------------------~~~-
'
214 f
6.7
FI R E PROTECTI ON INSPECTION ---------- --
- ------- ---- -------
215
!
6.8
!
6.9 ENV I RONMENTAL QU At.I F I C AT I ON - -- --- -- --- ---- -- ------ ----- -- - --- -
LIMITINC SAFETT STSTEM SETTINC_
l
Page No.
i SAFETT LIMITS
2.1 i
- - - - - - - - - - - - - -
-
- - - - - - - - - - - - - - -
!
1.1 FUEL CLADDINC INTECRITT - -
2.2
- - - - - - - - - - - -
REACTOR cootar SYSTEM ---------------------
i l
1.2
.
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Amendment No. 61 i
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I TABLE OF CONTENTS (Cin't)
t!MITING CONDITIONS OF OPERATION Page No.
SURVSILLANC_E
,
3.1 IRACMR PROFBCTION SYSTDI.
4.1
.................
.........
,
3.2 PNOTECTIVE INS'IRUMENT SYSTDtB.
4.2
...............
.........
,
.
I A.
Esergency Core Cooling System..............
A
.........
l S.
Primary Containment Isolation..............
a
.........
C.
Demeter Building ventilation Isolation and Standby Gas Treatment System Initiation
C
...........
.........
i D.
Air Ejector Off-Gas System Isolation
D
..........
.........
I E.
Control Dod Block Actuation...............
E
.........
F.
Nechanical vacuum Pump Isolation
r
............
.........
C.
Post-Accident Instrumentation.
G
.............
.........
N.
Drywell to 'IOrusAP Instrumentation..
H
.........
.........
I.
Recirculation Pump Trip Instrumentation.
34a I
........
..........
3.3 COIR!WOL RCD SYSTDI
4.3
.....................
.........
i A.
Reactivity Limitations
A
.................
.........
s.
Control mode......
s
................
.........
C.
Scram Insertion Times..
C
................
.........
D.
Control Dod Accumulators
D
................
.........
j E.
Wesetivity Anomalies
E
-
..................
.........
!
3.4 HEACTOR STAND 8Y LIOUID COstrmOL SYstet.
4.4
...........
.........
i A.
Norms 1 Operation
A
....................
.........
!
3.
Operation with Inoperable Components
B
'
..........
.........
l C.
Liquid Poison Tank - Boron Concentration
C
........
.........
.
l 3.5 COIIE AND CONTAllSEENT COOLING SYSTDIS
4.5
............
.........
l
...
.
.
!
A.
Core Spray and Inw Pressure Coolant Injection.
A
.....
.........
B.
Containment Spray Cooling Capability
a
..........
.........
,
j C.
Residual Neat Removal (RHR) Service Water System
C
....
.........
i D.
Station Service Water and Alternate Cooling Tower Systems
o
.........
j E.
Nigh Pr' essure Coolant Injection (HPCI) System.
E l
.....
.........
I
-
l AffENDMEND NO. 67
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vywr$
l TABLE OF CONTENTS
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l (cont inued )
[
>
LIMITING CONDITIONS OF OPERATION Page No.
Surveillance l
l F.
Automatic Depressurisation System.........................
F
................
!
G.
Reactor Core Isolation Cooling System (RC1C)..............
G
................
l N.
Minimus Core and Containment Cooling System Availability..
.........'.......
M
-
I.
Maintenance of Filled Disc ha rge Pipe......................
I
................
3.6 REACTOR COOLANT SYSTEN........................................
105 4.6
................
A.
Pressu re and Tempe rat ure L1mit a t ione......................
105 A
................
S.
Coo l a nt C hee 1 st ry.........................................
106
................
C.
Coo l a n t Le a ka g e...........................................
108 C
................
!
D.
S a f e t y a nd R e l i e f Va 1 ve s..................................
108 D
................
E.
S t r uc t u r a l I nt eg r i t y......................................
109 E
-
................
.
,
i F.
Jet Pumps.................................................
109 F
................
C.
S i ng l e - Loop Ope ra t i on.....................................
110 N.
Recirculation Systes......................................
110 I.
S hoc k S u p p r e s so r e.........................................
110s
................
.
J.
T he rma l-Hyd rau l le S t a b( 11 t y...............................
110b J
................
3.7 S TATI ON CONTA I N NE NT S YSTENS..............'.....................
126 4.7
................
l A.
P r i ma r y Con t a i nme n t.......................................
126 A
................
i B.
S t a nd by Ga s T r e a t me n t.....................................
130 B
................
'
j C.
S econda ry Co nt a i nme nt Sy st es..............................
131 C
................
D.
Primary Containment Isolation Valves......................
132 D
................
,
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- l Ame n.lme nt No. 6T 0 II-ill-
.
G
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_ _ -_
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VYNFS
.
TABLE OF CONTENTS (continued)
LIMITING CONDITIONS OF OPERATION Fage No.
Survet tlance
3.8 RAD I DA CT I VE E F F UU E NTS.........................................
147 4.4
................
f A.
Liquid Effluente Co nc e nt r a t i o n..........................
147 A
................
B l
3.
Liquid Effluente:
Dose...................................
148
................
149 C
j C.
Liquid Radwaste Treatment.................................
................
D 149
................
D.
Liquid Boldup Tanks.......................................
l E.
Caseous Effluente: Dose Rate.............................
150 E
,
................
F l
F.
Caseous Effluente: Dose From Noble Casee.................
151
................
!
C.
Caseous Effluente Dose,Froe lodine-131, todine-131,
,
C l
Trittue, and Radioactive Materials in Particulate Fore....
152
................
M.
Ca seous R adwe s t e T re a t me nt................................
152 H
................
j 1.
Ve nti la t ion Exhaust Trea tme nt.............................
153
................
J.
Emplosive ces Mixture.....................................
153 J
................
K l
K.
S t eaa Jet Air E jec t o r (SJ AE)..............................
153
................
154 L
L.
Primary Containment......................................
................
l M.
Total Dose................................................
155 M
................
,
N.
Solid Radioactive Weste...................................
156 N.
'
................
161 4.9 3.9 RADIOACTIVE EFFLUENT NONITORING SYSTEMS.,......................
................
,
A.
Liquid Effluent I ns t rume nt a t i o n...........................
161 A
................
!
B.
Caseous Effluent I n s t ruee n t a t i o n..........................
161a
................
l C.
Rad iol og ical Envi ronmental Monitoring Frog ree.............
161a C
................
D.
La nd U se Ce n s u s...........................................
162 D
................
163 E
l E.
Intercomparison Progras...................................
................
Amendment No. J), hf. 83-Iv-
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VTNP8
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i TABLE OF CONTENTS
l (continued)
LINITING CONDITIONS OF OPERATION Fase No.
Surveillance
3.10 AU1t LI ARY ELECYRICAL FOWER SYSTEMS............................
173 4.10
................
Al A.
No rma l Ope ra t i on..........................................
173
................
-
l
Ope rat ion with I nope ra ble Compone nt e......................
176
................
C.
D i e se l F ue 1...............................................
177 C
................
l
.
3.11 REACTOR FUEL ASSENBL1ES.......................................
180s 4.11
................
i
,
A.
Ave rag e F l e se r LMC E.......................................
180s A
................
l
- B.
LNCE......................................................
180b B
................
j C.
NCFR......................................................
180c C
................
i l
3.12 REFUELI NG AND SPENT FUEL MANDL1 NC.............................
181 4.12
................
A.
Re f ue l i ng I nt e r 1 oc ks......................................
181 A
................
,
B.
Co r e Mo n i t o r i ng...........................................
182 a
................
.
C C.
Fue l S t o rag e Fool Wa t e r Leve 1.............................
183
-
................
D.
Cont rol Rod a nd Cont rol Rod Dr ive Mai ntena nce.............
184 D
................
'
E.
EE t e nd ed Co re Ma l at e na nc e......... y.......................
IS4 I
................
F
F.
Fuel Movement.............................................
185
................
{
C.
C r a ne O pe r a b( 11 t y.........................................
185 O
................
M.
Spent Fue l Foo l Wa t e r Tempe ra tu re.........................
185e H
................
3.13 FIRE PROTECTION SYSTEN........................................
187b 4.13
................
.
I 5.0 DESIGN FEATURES....................................................
188
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6.0 AbHINISTRATIVE CONTR0LS............................................
1 90
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v-Amendment No.
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VYNPS i
1.
SAFETY LIMIT 2.1 LIMITINC SAFETY SYSTEM SETTINC b.
Flux Scram Trip Settinst (Refuel o_r Startup and Hot Standby Mode)
When the reactor mode switch is in the REFUEL or STARTUP position, average power range monitor (APRM)
scram shall be set down to less than or equal to 15% of rated
!
neutron flux (except as allowed by Note 12 of Table 3.1.1).
The IRM flux scram setting shall be set at less than or equal to 120/125 of full scale.
i
.
'
l l
l
!
I sb Amendment No. S A, Js' 90
'
.
.
. _
_
.
VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING B.
Core Thermal Power Limit (Reactor Pressure B.
APRM Rod Block Trip Setting 1800 psia or Core Flow I of Rated)
1.
The APRM rod block trip setting shall be i
)
When the reactor pressure is 1800 psia or as shown in Figure 2.1.1 and shall be:
]
core flow $10% or rated, the core thermal RB 1 66W + 42%
S power shall not exceed 25% of rated thermal i
l power.
where:
I l
C.
Power Transient rod block setting in SRB =
i I
To ensure that the safety Limit established percent of rated thermai in Specification 1.1A and 1.1B is not power (1593 MWt).
exceeded, each required scram shall be percent rated drive flow initiated by its expected scram signal. The W
=
where 100% rated drive safety limit shall be assumed to be exceeded flow is that flow when scram is accomplished by means other
equivalent to 48 x 10 than the expected scram signal.
lbs/hr core flow.
In the event of operation with the ratio
!
of MFLPD to FRP greater than 1.0, the l
APRM gain shall be increased by the l
ratio: NFLPD
'
i FRP where: NFLPD = maximum fraction of limiting power density l
where the limiting power density is 13.4
kW/ft for 8 x 8 fuel.
'
l fraction of rated power FRP
=
(1593 MWt).
- Amendment No. p(' 90
,
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l
~.
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______
_ _ - _ _ - _ - _.
_ _ _ - _
.
VYIfPS
.
i 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTINC
_
l In the event of operation with the ratio j
of MFLPD to FRP equal to or less than 1.0, the APRM gain shall be equal to or
j
,
greater then 1.0.
i i
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6e Amendment. No. p' 90
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l 1.1 SAFETY LIMIT.------
2.1 LIMITING SAFETY SYSTEM SETTING D.
Whenever the reactor is shutdown with irradiated C.
React'or low water level screa setting shall 'he at fuel in the reactor vessel, the water level shall least 127 inches above the top of the enriched not be less than 12 inches above the top of the fuel.
enriched fuel when it is seated in the core.
D.
Reactor low-low water level Emergency Core Cooling
.
System (ECCS) initiation shall be at least 82.5 inches above the top of the enriched fuel.
,
E.
Turbine stop valve scras shall be less than or equal to 10% valve closure f rom full open.
,
F.
Turbine control valve fast closure scram shall, when operating at greater than 301 of full power, trip upon actuation of the turbine control valve fast closure relay.
C.
Main steam line isolation valve closure scram shall be less than or equal to 101 valve closure
'
from full open.
H.
Main steam line low pressure initiation of main
-
i
!
steam line isolation valve closure shall be at i
least 800 psig.
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!
7-Amendment No, 68. 84
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e
- _. _ _..
. - - -..
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,..
H l
~
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I! -
.
Figure 2.1-1
-
-
..
.
-
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.
.
-
a.=d
.
'
AFDi. Rod sloc'd Settint.s k..- (
.
.
f G,J
-
..
r.. -
.
l{
-
-
,.
D e@;
-
-
-.
uu
'
130
,
M-d,,
-
- 15 K:
120
-
- 42
29
. p-
.,,
110
-
?;
b..
1'.t
.
-
-
f.
100 l
!.TE! Ilow Elised Scrtn g
.
e}
}
-
50 -
$:t~-
g
~
st.-
- s
.
<.
u
..
-
uc 80 - -
- .-
-
u APRM Rod Block
..
'"
!:'
.
k,'
.
e4,
-
.
.
,
li
/
f
,
,
-
3'
-
- -. L
.
.
e
-
6. :'
.
O
.
E..
M U
.li
-
50
-
'
. r
.
-
-
ji t.s.
__
i
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.
r. [1)
-
)Y.
t: %'
..
$.
-
I
..
L..
.
i:Y
-
..
'
1;;
-
!N l
- .'
.
.
.
,
-
Id
.
-
-
- -f
.
t i
i :,
t
C
40
80 100 120
,
,
-
la
g4 i
F.ecirculation Flov (1 of design)
-
.
Ig
'
..
~
fI:fh,.
.
.
.
.
e3
.
W
,
1.. *s (
hDY 1 g
,
..
.
.
i
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i..
.
,
,
.-
.. 1
- :4
--
- ~ -
-
.._ _,_ _
' - * * - ' " ' "
-. - - - _,,,
_ _ _ _
-___-_
_ _ _ __
.
<
.
VYNPS i
'
'
3.7 LIMITING CONDITIONS FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS 4.7 STATION CONTAINHENT SYSTEMS l i 3.7 STATION CONTAINHENT SYSTEMS I
A'pplica bili t y :
l Applicability:
'
Applies to the operating status of the primary and Applies to the primary and secondary contalement
+
!
'
secondary containment systems.
system integrity.
j
.
'
'
Objective:
,
Object ive :
l e
i To assure the integrity of the primary and To verify the integrity of the primary and secon-i
'
I secondary containment systems.
dary containments.
!
!'
Specification:
Specification:
i
!
$
A.
Primary Containment A. Primary Containment
'g l
I 1.
Whenever primary containment is required, 1.
The suppression chsaber water level and tes-the volume and temperature of the water in perature shall be checked once per shift. A
'
the suppression chamber shall be maintained visual inspection of the suppression chamber
.
within the following limits:
Interior including water line regions and
'
g the interior painted surfaces above the
,
I Maximum Water Temperature during normal water line shall be made at each refueling
'
'
a.
operation - 1000F.
outage. Whenever there is indication of'
relief valve operation which adda heat to, b.
Manipum Water Temperature during any the suppression pool, the pool temperature test aperation which adds heat to the shall be continually monitored and also ot-
,
l l
suppression pool - 1000F.
served and logged every 5 minutes until the bect addition is terminated. Whenever there t
i i
c.
If Torus Water Temperature exceeds is indication of relief valve operation with
.
Il00F, initiate an immediate scram of the temperature of the suppression pool l
the reactor. Power operation shall not reaching 1600F or more and the primary
be resumed until the pool temperature coolant system pressure greater than 200 i
is reduced below 1000F.
ps!g, an external visual examination of the
'
'
suppression chamber shall be conducted
,
before resuring power operation.
!
d.
During reactor isolation conditions, the reactor pressure vessel shall be depreneurized to less than 200 pelg at
-
i
!
~
normal cooldown rates if the torus j
t water temperature exceeds 1200F.
i
'
-
Amendment No.jkd',88 126
..
esea
.
.
.,
3.7 1.lHITIt!C CONDITTONS FOR OPEltATIOil 4.7 SURVI'ILLANCE REQUIREHENTS
- '.
e.
Minimum Water Volume - 68,000 cubic feet 4.7 STATION CONTAINHENT SYSTEMS f.
Maximum Water Volume - 70,000 cubic feet 2.
The primary containment integrity shall be demonstrated as required by Appendix J 2.
Primary containment integrity shall be' maintained to 10 CFR Part 50 The primary containment at all times when the re.ictor is critical or when shall meet the containment acceptance t h.
reactor water temperatur e is above 212 l' and requirements set furth in tha, appendix.
f ui:1 is in the reactor vesuel except while performing low power physics tests at atmospheric pressure at a.
Penetrations and seals listed in power 1evels not.o exceed 5 Hw(t).
Table 4.7.1 shall be leak tested
~
at 44 psig (Pa),
b.
Type C tests shall be performed on the
-
isolation valves listed in Table 4.7.2.a.
'.
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.,
-
.
- Amendment No. 50 126a.
.
.
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VYNPS 3.12 1.lfilTibG CONillTION F0lt OPERATION 4.12 SUltVETI,LANCl! REQIIIREMiiNT 3.12 l'.!".Fhl. LING AND SPl!NT FUEL llANDLING 4.12 Rl!FUP. LING AND SPl!Prr FUI!L !!ANDI,ING Applicability:
AppiicabiIity:
Applies to fuel handling, core reactivity Applies to the periodic testing of tho* e !nterlocks lirui ta tions, and spent fuel handling.
and instruments u;cd fduring refue ling and to the testing of the reactor building crane.
j ective:
O Objective:
To a:::.nre core reactivity is within capability To verify the operability of instrumentation and o f t h:.: control rods, to prevent criticality
.nterlocks used in refueling and the operability during refueling, and to assure safe handling of the reactor building crane, of spent fuel casts.
.
Syreific.ition:
Specification:
.
-
A.
Refueling Interlocks A.
Itefueling Interlocks
-
The reactor n: ode switch shall be locked Prior to any fuel handling, with the llcad off
,
in the "itefuel" position during core the reactor v.cssel, the refueling interlocks alterations and the refueling in'tcrlocks, shall be functionally tested. They shall also
-
.
1isted below, shall be operable except be tested at weekly intervals thereafter until as speci fied in Specificat ions 3.12.0 no longer required and following any repair work associated with the interlocks.
and.s.12. li.
,
1.
Control Itod Blocks flode switch in Startup/Ilot Standby a.
and refueling platform over the reactor.
18i
.
faen+ nnt No.
"o
.
-
_. -
.-. =__
.
.
.
VYMPS
.
29 l 3.12 LIMITING CONDITION FOR OPERATION L.12 SURVEILLANCE P.EQUIREMENT
.
b.
Fuel on any refueling hoist and refueling platform over the reactor.
c.
Mode switch in Refuel with one
-
control rod withdrawal permit.
2.
Refueling Platform Reversg Motion (toward reactor vesnel) Pled a.
Mode switch in Startup/ilot Stand-
- - -
by.
e b.
Any c'ontrol rod out and fuel on
.
any refueling hoist.
,
,
"
3.
Refueling Platform lloists Blocks
.
Any control rod out'and fuel on a.
any refueling hoist over the vessel.
.
b.
Iloist overload.
-
,
.
c.
High position limitation.
.
B.
Core Monitoring B.
Core Monitoring During core alterations two SRM's shall Prior to making any alterations-to the be operable, one in the core, quadrant core the SRM's shall be functionally where fuel or control rods are being tested and checked for neutron response.,
,
.
.
t e
182
.
f'
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-... _. _
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as
..o i
.
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J
)
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t I
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T1NPS
.
4.32 SilRTEILLAIICE REtyttBetif_f
.
L13tlTIWS tRIIDITION FOR OPERATIOII
'
3.12
.
Thereaf ter, the Sigle shall be cheeled deity
,
For en SIDE
_
sowed sad ese la en adjacent gesedrent.
f or reopense.
-
to be ceasidered operable the f ollowiss condittene
,
.
l, l
eheti he estisfiede f.
The Sise shell be imeerted to the norset
!
1.
(llee of speetet movable, operatise level.
deakiss type detectore derisg initial f eel i
leading and sejer core etternstlene in piece of mesual detector le permiselble se less as the detectore is eennected late the proper
'
etetustry which eestein the regelred red bleche).
- The SIst shall have e staleen of 3 eps with
.
2.
ett sede fully inserted in the core.
Prior to aptrel solandise or 'r'eleindise, th Prior to Pr,ter to spiret enleedise, the Slgte shall be SRNe shall be fonettenelly tested.
optral releedise, the SENs shaft be checked 3.
preven operable as otsted in Sections
.
-
-
3.12.3.1 and 3.12.3.2 she,e. however, decise ier meetron roepease.
optral seleedtog the comet rate esy drop
,
'
belos 3 cye.
.
.
Frier to spiret releedisg, too diesenstly
adjecost feel seeembites, which have previesely acessuteted esposure in the reseter, shall be leaded into their deelgented core peettiene neat to each of the Unti1
,
g 4 SaNo te obteta the required 3 cpe.
-
l these eight headles have been leaded, the 3 eye regelresent is set necessary.
Ptsel Storese Feel Water Level
,
C.
Feel Storete Fool Water Level
.
Whenever irradiated f eel te etered in the
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C.
_Utemaever irradiated feel le stored is the f uel eterese peel, the poet level shell be
.
resel eterage poet the poet ester levet shall recorded daily.
103 be selsteined et e level of et least 34 f eet.
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Amendswant.l*>. 59 77
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4.12 SURVEILLANCC Rt0UIRFt1ENT
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D.
Control Rod and Control Rod Drive >bintenance D.
Control Rod and Control Red Drive Maintenance
A maximum of two non-adjacent control rods 1.
Sufficient control rods shall be withdrawn
.
i prior to perforning this maintenance to
.
separated by more than two control cells in any denonr.tente with a margin of 0.25 percent direction, may be withdrawn fron the core for Ak that the core can he made suberitical the purpose of perforning centrol rod and/or any timo during the maintendnce with t
at control rod drive maintenance provided the the utrongest operable control rod fully,
following conditions are satisfied:
withdrawn and all other operable rode
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1.
The reactor mode switch shall be locked fully innerted.
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in the " Refuel" position. The 2.
Alternately, if a minimum of eight control refueling interlock which prevents rods surrounding each control rod out of more than one control rod frem being service for maintenance are to be fully
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withdrawn may be bypassed for one inserted and have their directional control
_ _ _
of the control rods on which maintenance valves electrically disarmed, the 0.25 is being perforned. All other retucling percent N4 margin shal1,be met with the
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interlockn chall be cperrble.
l strongent control rod remaining 14 service
during the maintenance period fully with-2.
Specification 3.3.A.1 shall he net,
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drawn.
l or the control rod directional control valves for a minimun of eight control rods surrounding each drive out of service for naintenance shall be dis-
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acced electrically and sufficient
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nargin to criticality denanstrated..
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3.
SRMs shall be operabic (1) in each core quadrant cent.atnin~ a control rod
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on which esintenance is being per-formed, and (b) in a guidranc adjacent to one of the quadrants specificJ in
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,29 l Specification 3.12.n. 3. (a) above, nequire-
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ments for an SR:4 to be conr.iderad operable
,
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are given in Specification 3.12.3.
.
E.
Er. tended Core Maintenance E.
Fxtended Core Staintenance
.
prior to control rod withdrawal for extended 1: ore than two control rods rav be ufth-drawn f rc, t! c reccter cora provi<'ci. cl c core -1tntenance, that contr'o1 rods control cell rnall be verified to contain no fuel
f u11cuir.q cemditien are r.
c ;.:f ;ed:
a s sechl ie:n.
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4.12 StMITE11.tANCE REtp1RSIB9ft'
f LIIIITIWB MTISE FUR 0pBRATICII
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I 3.12
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This serveillence requirement le the sees se l
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The resetor mode switch shell be locked in that given in Speelficaties 4.12.A.
i 1.
The refuelive I
the " Refuel * Posittee.
,
I interlock which prevente more then one
.i control red free being withdrawn may be
!
bypeseed en a withdrawn control rod of ter the l-fuel seeeeblies la the cell containing j
(centrolled by) that control rod lieve been
All other
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reeeved free the reacter core.
refuelleg interlocke shall be operable.
i This serveillence regeltesent le the some se
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2.
SIsto shell to operable la the core quadrant that given in Specificetten 4.12.3 ehere fuel er control rede are helse moved, l
2.
The
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and to en adjacent goedrent.
requirements for em SRM to be considered i
operable are stven in Speciflestion 3.12.3.
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If the optrol onload/releed method of core
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3.
alterettom is to be used, the fellowing f
eendittene shall be meet
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Prior to spiral soloed and rulsed, the
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SRMe shell be proven operable se stated s.
in Specification 3.12.51 sad 3.12.82.
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f however, during spiral unloadies, the eeket este soy drop below 3 cys,
'
The core any be optrolly releeded to b.
f either the original configuration or e dif ferest eenfiguration in the reverse i
segsence of that need to unload, with i
the enception that two (2) diagonelly adjacent fuel aseeablies, which have
,
previewely occuentated esposure in the reactor, ehell be loaded into their i
deolaneted core positione next to each of the four (4) SRMe to obtain the required 3 cya. Until these eight (8)
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185 bundles have been loaded, the 3 cpe requirement le not neces se ry.
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4.1) SURTE1LLANCE Mqt1MpgNf_
3.12 LIMITEWS MOR FOR OPERATION i
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I Followlag leserties of the lettle1 sight
,
S (s) bundles, the reactor will be eptretly releeded fran the center cell (
esteerde, entti the core le fully loaded.
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T At least SOE of the fuel mesemblies to
,
l e.
be releeded late the core shall have l
previemely occumelsted a minioue
.
l espeewre of 1000 nud/T.
<
l F.
Feel Novement_
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F.
Feel Meeeeemt
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Frier to say feel headlias or sevement le the -
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Fuel shall set be moved er handled in the reacter core, the licesoed operater ehe11
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reacter eers for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following reactor verify that the reactor has.boes le the cold
,
ehetdown to cold ehetdown conditions.
ehetdeve condittee for a mistown of 24 hoore.
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C.
Crane Operability C.
Creme Operability Within see meeth prior to opget
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1.
a.
1.
The teacter Building crene shall be feel cook hendling operations, se
,
operable eben the crane le used for inspecties of crees cables, handissa of a spent feel cook.
sheeses, book, yoke, and cook Ittting truantone will be mode.
These leapectiene shall aset the requiremente of Aust standard 185-e
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Amendment No. 59
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Stmvt111 Aart 3B451353NT i
4.12 EfW171NO CONDIT10N Fet OPERAfton 3.12
'.
330.2, 1967 A etene rope shall to
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replaced if ewy of the replacement
criterie gives in ANB1830.2.t> 1967 are set.
I Iso-leed escheedeel med electrical l
b.
teste will be conducted prior to t
Ilftlag the empty caek free ite trenoport vehicle te verify proper jl operation of creas teatrele, brakes l
t end itftisg speede. A fwattienol
.
test of the creen bestes will be conducted each time se empty esek
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is litted clear of its treosport l
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vehlete.
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2.
Crane Travel 2.
(*reme Travel _
Crane travel limiting mechanical steps
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shell be lastelled on the cross trolley Spent feel cooke shell be prohibited refle prior to cask handlias operet'iene
free travel over irradiated fuel to prehlbit esek travel over irradiated
'
seeesbifes.
fuel eseembiles.
Spent Feel Feel Water Temperatere_
M.
Spent Feel pool Water Temperature Whenever irreddeted feel le le the spect feel 5.
Whenever irradiated fuel le etered in the pool, the pool water toeperstwee shall be If the peel water recorded delly.
opent fuel pool, the pool water temperature temperature reaches 130*F, all ref ueliss 1500r.
shall be salateined below operstlene tending to raise the pool water temperature shell cease end seneeres tekee lamedtetely to reduce the peel water temperature below 150*F.
189-6
.
Amendment No. pp 77
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discipline or Icem the f
i Designated alternates shall be from other plant personnel in the appropr ate
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) l te members servins en the -
I f, 5. Technical Services Croup; however, there shall be no more than three (3 *a terna
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!g cessittee at say one time.
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!F 6.
Deepensibilities_
Review all proposed estatemence Deview proposed normal, abnormal and coergency operating procedures.
d procedures or changes l$
procedores and proposed changen to thnne procedures; and any other propose a.
l ft therete se determined by the Plant Manager to af fect nuclear sa e y.
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Review proposed teste and experimente.
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Deview proposed changes to Techr.ical Specificattone.
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t hich changes would require a i
.c.
Review proposed changes or medIfications to plant systems or equipment, w I
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d.
j change in procedures in (a) shnve.
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j Review plant operations to detect any pntential safety hazarde.
h investigatione to include
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Investigste reported instances of violations of Technical Specifications, sucManager of Operation
.
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reporting, evolwation and recommendations to prevent recurrence, to t e f.
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Figure 6 1 1).
sted by the Chairman of Perform special reviews and investigatione and render reports thereon se regne
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the Nuclear Safety Audit and Review Committee.
l
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7.
Authority The Plant Operation Review Committee shall be advisory.
l or dieeppreest of a.
The Plant Operation Review Committee shall recommend to the Plant Manager approva proposale under Iteme 6 (a) through (d) above.
Operetten Review Committee and l
b.
.
l In the event of disap,reement between the recommendatione of the Flantd by the plant Manager to
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. a the actione contempleted by the Flant Manager, the course determ ne the Manager of Opefations.
1.
f more conservative will he followed with immediate notification to
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S e plant Operation Neview Committee shall m..e centativo detscrinations co t3 whether or not e.s,. 4sh is determin
f considered by the Committee involve unreviewed safety questions.
e.
g review by the nuclear safety Audit and Deview Committee.
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Secords
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Minutes shell be kept at the plant of all meetings of the Plant Operation Review Committee and copies sha h'
be sent to the Manager of Operations and the Nuclear Safety Audit and Review Committee.
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i s. uselear safety Audit and moview committee He Committee shall consist of at least six (6) persons
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1.
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.
a.
Chairmen
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I b.
Vice Chairman
.
Feur technically quellfled persons who are not members of the plant staf f.
e.
l No more than three members shall be selected from the organisation reporting to the Mensger of
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Operations. -
he Cesmittee will obtain advice and counsel from scientific or technical personnel employed by the Company or other organizations whenever the Committee considers it necessary to obtain further e.'
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scientific or technical assistance in carrying out its responsibilities.
H e Committee membership and its Chairman and Vice Chairman shall be appointed by the Yankee leuc
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l services Division Vice President or such person as he shall designate.
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Qualifications De Coasnittee shall consist of a minimum of sin (6) members or designated alternates who as a group
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espertise in the following areas
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Nuclear Power Plant Technology
,a.
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b.
Reactor Operations
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Utility Operations
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VYIIFS d.
Fever Fleet Design Reactor Engineering e.
f.
Redietten Safety 3.sety Analyste
Isotrumentation and Centrol b.
1.
'Metellurgy Semi-seeuelly sad as required es cett of the Chetrues.
3.
IIeettaa Frequency _:
Chatraen er Vice Chatraen plus four esehere er deelgested alternetes.
4.
43merust 5.
Responeibttttles t
Review proposed changes to the operettag ifcease includies Tschetcal Speelficet ene, e.
Review minutes of meetings of the Fleet Operetten Review Committee to determi considered by that censtttee involve unreviewed er maresolved oefety questione.
b.
d under the Review the oefety evaluettene for cheages to equipment er erstees canylote i
CFR to verify that such actices did est const tute en c.
50.59 10 provielene of Section wereviewed eefety question.
h Pertedic audite of taptementies precedures, shell be perfereed under cegatsence of Included in these audite, but est limited to, are the followtas specitte d.
Ceemittee.
activities:
1.
plant ope ret tone;
.
factEtty f tre pro'tection progree; 11.
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Amendeent No. II, J(I,
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TTilpS tit. the redtelegical envireemental meetteries progree see the seemits thereof at least once per 12 months;
.
iv.
the of f-site Deee celestattee Meeman and leptementing precederse et least esce per 24 monthe; the Procese Centrol Fregree sad Septemaattaa precedures for proceoolas and pockestag f
v.
of redteactive weste at least once per 24 monthe:
i
vt.
the performance of activittee regelred by the quality asemeseee Fregree to meet the i'
prowletens of Regulatory Gelde 1.21. Restolen 1, Jees 1974, sad Regulatory Guide 4.1, Revielen 1,* April 1975, at least esce per 12 emethe.
Investigate att reported testances of violettees et Techsteel Specif tsattees, reporties
.
I e.
l fladtage amt receumendettene to provoet recorrence to the IIeeeger of Operettees.
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f.
Perfere special rewteme and levestisettees med reader reporte therese se regnested by the j
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Manager of Operatione.
I Review proposed teste and esperteente and reestte thereof when applicable, j
g.
y
.
j h.
Review abnormal performance of plant equiposet and seneettes.
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Review eauseet ec'currences and f acidente uhtch are reportable under the previelene of 10 CFR Fort 20 and 10 CFR* Fort 50.
i J.
Review of occurrences if safety itelte are escoeded.
6.
Amtherity
,
i Review propeeed changes to the operettag Itcense tacledtag Techetcal Spectiteettene and s.
restmed bases for euhetttat to the NRC.
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Review proposed changes or modificattoes to plant eyeteos or equiposet, provided that such changes or modificatione de met favolve unrevleued safety queettene.
198
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Amendeent No. 66,16
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i Receansed to the Itenager of Operettene appropriate acties to proveet reserveete of soy i
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violettees of Techetcel Speelficettene.
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Eveleste actione takes by the Fleet Operettee Review Cemetttee.
.
7.
Recorde Cet ee of the eisestes shall be~
t Nientes of all meetings of this coesittee et 11 he recorded.
forwarded to the Meneger of operettoes, the Vice Freeldent - Operettone, the Fleet IIsoeger eed i
eey othere that the Chatraea may destamete.
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1988 Amendment No.
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(3.3 ACTI0li TO P.C tar.CP it! T;!r EvCMT OF ?. !C PO:lTARt0 DCCullRIllCC Ill PLANT HPfRAll0N J
Applics to administrative action to be followed in the event of a reportatile in.currence in Plant operation.
j l
Any reportable occurrence shall be reported to the Nnager of Oln:ratioens and steall be reviewed by the Plant
)
Operations Heview Committee. This CameltLee steall prepare a sep.irali, sequentially numbered, report
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for c.ach reportable uscorrence. Each report shall slescribe the cirism:r.t.iin.cs leanling up to and resultleg i
freie the occurrence. Liut corrective action taten by the shift, an alleinpt in elelieu. the cav.e of the sw.currene.e. and shall res.usemend appropriate action to pi event or rc.lin.e lier pa s.lealillity of.i repetition
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of time occui rence.
)
Copies of all such reports shall be submitted to the Chatraian of the leuclear *>.ifety Audit and Review Committee for reviev and to the Manager of Operations for review and approval of any recomsmendations.
,
f.C_1_I_Oll TO RC TArtil if A SAFETY LIMIT 15 CXCfEDr0
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Ahplies to adminti.tr.iLive action in be followed in the event a s.ifely limit 1. cuaieded.
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If a ;af e;y limit is exci edeal. the reactor sh.ill be sluitdown imem ili.ili:ly.. An imin.liale report shall !..-
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mide la Llic Hanager ol' Operations. A complete analysis of Llie circienstatu es Ir.eding up to and result.ng
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j f rise the situation together with reconsuendations ley the plant Operations I:eview Cineilttee shall also 1.e l
' prepared.
This report stia11 he sulanitted to the Nnager of Operations and the Chainman of the Nuclear
' afe'.f Audit and Neview Comenii. tee.
.
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'Icactor operation shall not be resumed until aulliorized by the U. 5. Iluclear RCgulatory Comenission.
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TVMFS
6.5 Fleet Operettaa Frecedures Betailed writtee precedures, tevelsteg both euclear and ese auclear eefety, lectedtes appliegble A
check-off itete and instructione, covertes arose listed belee shall be propered and approved.
j
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All precedures shall be adhered te.
1.
Idermal startup, operetten and shutdeve of systeme med campeeente of the facility.
2.
gefeeling operettene.
3.
Actione to be tekee to correct specifte sad foresees poteattet selfeectices of eyotees or esepeneste, suspected Frieery Systen leaks and ebessent reactivity chsages.
4.
Beersency condittene levolving poteettet er actual rolesse of redteactivity.
.
Preventive and corrective metatenance operettene ektek could have se effect se the safety of the 5.
reactor.
.
6.
Servet11ance and teetles requiremente.
Fire protectise progree Septementattee includies ateless fire brigade regetressete end trateles.
7.
The treintas progree shall eget er exceed the requiremente of Section 27 of the SFFA Code 1976.
Treintes seestone otti be scheduled as plant operettene result het util be completed to specified subjects annually. Inittet ttre brigade tratetes shall be completed by March 13. 1978.
S.
Procese Control Fragree in plant toplementattee.
9.
Off-Site Deee Calculotten Manual te plant Septementatten.
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TTEFS
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godtattee centrol standarde and precedures shall be prepared, approved and estatetoed and made
i 3.
l evettable to all stettee pereennet. These precedures shall show peraleetbis radiaties espeemse, and I
shall be coastetent with the regetroments of 10 CFR Fort 20. Yhte radiaties pregeettee ye ehet!
t l
be ergesteed to meet the requiremente of 10 CFs part 20.
peregraph 20.203, "Caettee signe, labele, eigeste and centrole". In lies of the "seatsel device"
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er "alere signe1* regelred by peregraph 20.20)(c)(2), each high radiaties ares to alnich the
,
toteestty of redlettee le 1000 ores /br er less shall be horricaded sea conspiceneely posted as a
high redlettee eres and entrance therete ehe11 he centrolled by requiries teemence of a Radietten Work Ferett.e Any individual er group of tedividuate permitted to enter each erase abelt he
l provided with one er more of the fellemings
l A radlettee moettertog device which centlememely tedicates the rediettee dose rate to the e.
l
area.
A radiettee soottoring device utnich coattamenely tetogrates the radiettee does rate to the
.
b.
integrated dose is received. Retry tote each areas with thte eres and eterne when a preset meetterling device any be made ef ter the dose rate levele to the area have been estabitehed
and perseemet have been made knowledgeable of them.
i A Realth Phyelce queltfled tedividual (t.o., geellf Red to radiettee protectice precedures)
t
,
c.
with a redtattes deee rate meelteries device she to reopensible for psevidles peettive
!
control over the activities withis the area med eine wt11 perfees pertedte redtattes'
servet11ence at the f requency specified to the gWF. The servettlance f regeoecy will be
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estabitehed by the Flest* Meelth Phyetelet.
f The ebeve precedere shall slee apply to each high radlettee eres to mentch stie toteestty of
',
rediettom to greater than 1000 mese/hr. le addittee. locked doore einett he provided to provost eneathertsed entry inte each stese med the keye she11 he estatetoed under time adelaistrettwo centret et the Shif t Supervleer en duty and/or the F1 set Ilealth rhyeletet.
.
- IIeelth Physico peresseet eine11 he esempt f ree the gWF teemance requirement during the performance of their seelsned redtatten protection dettee, providing they are fellontas pleet redtattee protectica precedures for entry inte high radiet tee areas.
201
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Amendment lie. 36. )(.
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VVlors
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l C.
Precedures prepared for A and g above shall be reviewed and approved by Else Fleet Blanager, or bis designee, and Lt.e Hansger o f Operet tene.
la. Temporary cliences to precedieres described in Specification 6.5.A above which de not chesige the Intent of the ortgleet precedere, may be mode witle alie concurrence of two lustividuele Seeldleeg senter operator licensee. Such clienges elsell be documented and subeesguently reviewed by the F0 llc and og proved by the Plant 9tansger er 3 le designee.
E.
Temporary changes to precedures described in speelfication 6.5.3 may be maele vitti the concurrence of en ladiviehaal holding a senter eyeaster license and the liest tle phyelclet oss duty.
F.
Licensed redleective sealed outerces aliall be leak testeel f or contamination. Tests f or leakage and/or contaaliset ten eteel t be performed by the licepsee or by other perenne specifically autherleed by the theelesian ur en agreement state as f ollows:
1.
Each licensed sealed eeurce, accept startup sources previewely enhjected to core flue, costelming redleective materiale, ottier then 18ydrogen 3, with half-lif e greater then thirty days and in say form, other t hen gee, shell be tested f or ler.kege and/or conteelnatleen et intervate nut to escoed ele monthe.
2.
We perledic leak test resgulted does not apply to oested sources that are stored and are met belns used. The soeerces esempteil f rom t hle t est shall be t ested f or leakage prior to any seee er t ransf er to another user unless they have been leak tested within six months prior to the date of use er transfer, la the abeence of
.
e certificate f rom a treneferrer ludicating that a leak test has been made within ela mentbo prior to the t renefer, sealed sources shall niet lie put list e use weit i l t es t ed.
3.
Each sealed startup seeirce shall he t esteil within 31 days prior to lecing enbjected to core fina and f ollowing repai r or maintenance to t he source.
i
%e leakage test elsell be capable of eletect ling t he presence of 0.005 elcrocurle of radleective material en tiee test onople.
If the 'teet reveals t he presence of 0.005 microcier t e er more of removalile conteeluellen, i t eks i l l amed i a t e l y be w i thdrawn f rom use, decontaeles.st ed, n ei.I r epai red, o r be d i sgioned o f i n accur al.ooece wi t h Caenl eelen regulet t one,
' toutwithstanding the periodic leak test s respelred by thle Techselcol Specificat ion, seiy licensed eested source le except f reis siecle l eek t est wlsen t he source cont alise 100 elcrocuries ur leone at het a menl/ar gamme celt ting meterial or 5 microcuries er less of alpha celt t ing; e.ilcr ial.
A sperInt report s hal l he p re pa reil a n.l sul. ail l i cil t u e lse Cnemal eelun wi t hl ei % st a y s i l ann e r e lenhage t est e reveal t he prencat e of 14.00% mi rr urier ic s n1 s o mov.el.l e e niit nieleina lun.
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Aneniinient flo.
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6.4.
rf. ANT OPERATING RECORDS
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Records and/or logs relative to the following items shall bo h.ept in a manner co.ftenient for uteb A.
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and.shall be retained for at Icast five years:
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Records of normal plant operation, including power levels.end periods of operation at each l
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power level.
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Records of principal maintenance activit'ics, including inspection and repair or p'incipal items of
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equipment pertaining to nucicar safety.,
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Records of reportable occurrences.
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Records of periodic checks, inspection onJ/or es11brations perfonned to verify that surveillance i
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requirements are being met.
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Records of any special reactor test or. experiments.
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Records of changes made in the Operating Procedures.
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Records of radioactive shipments.
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3.
Test results, in units of microcuries, for leak tests performed on licensed sealed sources.
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Results of annual physical inventory-verifying accountability of licensed sources on record..
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Records and/or logs reistive to the following items shall be re' corded in a manner convenient for review and shall be retained for the life of the plant:
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Records of su'bstitution or replacexnt of principal items of equipment pertaining.to nuclear safety.
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l Records of changes and drawing chan{es mado to the plant as it is desdribed in'tius' Safety Analysis 2.
Report.
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Records of plant radiation and conta:sination surveys.
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P.ccords of new and spent fuel inventory, transfers of fuel, sind assemb!r 'historie.i.
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itecords of radioactivity in liq Id and casenus wastes relessed N the.....
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6.- P.-rerds of radiation expo.ure for all plant personnel, includi..:..i.
s. actors. t.r.J isitors to
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the plant in n corl;*nce: uith 10 CI:I! 20,
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Recorde of tremetent er operettemel cyc1tes for these pleet components that beve been destaned te I
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operate oefety for a lletted number of treestants or operettoest cycles.
Recorde of inservice toepecttone of the reacter cooleet eyotes.
S.
Minutes of meettage of the Fleet Operettee Bowlev Cemetttee med the Wacteer Safety Audit med l
9.
Review Seerd.
Recorde for Bestressental quellficettee which are covered under the previeless of peregraph' 6.9.
19.
I Recorde of emelyste reqetred by the Radiological Eevitessental IIsotteries Fregree.
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6.7 Basertion seestressets
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Is addities to the applicable reporttag regelremente of Title 10. Code of Federet tegoleggene. the of felleutes idsettfled reporte shall be estettted to the Strector of the appropriate Reglemet g, Isopectice med Beforcement malese otherwise ested.
A.
Bestise Begeete
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1.
Starter tapert
& esemary report of pleet startep and power eccelettee teettag shall be omheitted followtag
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(1) receipt of se operettag Itcesee. (2) assedeemt to the Itcease levolutas e plassed tecrosse le pesar level. (3) teatellettee of feel that has a dif ferent deelse er has hoon esenfectered by a l
different feel sappiter, and (4) modificettoes that any have alg,elflesetir sitered the onclear.
thermal or hydroelle perferesece of the pleet. The report shall addrese each of the teete identified to the FSAR and shell le general, teclude a descripttee of the messered values of the
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operettes condittees or charactertatice obteleed dettaa the teet progree med a couperteen of i
these velees with deelse predictione med spectiteettoes. Amy corrective octless that were
j regelred to obtete settof actory operettee shall else he described. Amy additiesel spectite i
detette regelred in Itcease condittene beoed se other cemetteente obsti he teetoded to this j
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Startup reporte ehell be enheitted withte (1) 90 days followleg esoplettee of the etertup test progree. (2) 90 days fetteeles reeempttee of ceassacement of commerclet power operettee, or
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(3) 9 meeths fellestag lettlet criticality, etichever to eartteet. If the etertup report does est cover ett three evente (i.e.
lettlet ertticality, complettee of etertop teet progree, and resumptien et commencesset of commercial poser operettee), supplemoetery reporte sheit be i
solmitted at least every three meethe matti ett three evoete have been completed.
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Aseedeemt No. )( 63 l
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2.
Asseet sepert As seemel report coverlag the prevlees calender year shall be entiettted peler to IIerch I of each The seemet report shall f eelude a taheletten en se sommel heele of the engby of stetten, stility sad other peroommel (teclosetas centracters) recetweeg esposeres geester elles 100 areelyr year.
I/ e.g.,'seector med their associated men-ree esposure accordias tc. merk med job imeettees e
operettees and servestleece, feeervice toepectice, reetfee estatessace, special estatessace The dose seetseesset te vertees duty l
(describe meistemence), meste preceostas, and refemellas.
Smell l
feectione any he estimates beoed en pocket doelmeter TLS er file hedge seeeeeeeeet.
In the i
esposeres tetelleg lees then 201 of the tedividual total deee need est he seesented for.
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aggregate, et least SOE of the total ehele body dose received free enternet eserces shall be
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asalgaed to specific enjer merk functlene.
3.
Heathly operettaa sepert I
Bestine reporte of operettas stattetice med etnetdeus espertence shall be sentaitted on a meathly
l heels to the Of fice of Management Inf ormattee and Fregram Control. W.S. Eaclear Regulatory Ceemiselen Weehlagten. D.C. 20555, eith a copy to the appespriate Beglemet Of fice, to sertve meTh*ese
later them the fif teenth of each month felleelse the celeeder seath covered by the report.
l reporte shall Secliede a norrettwo enamery of operating esperleece derlag the report perted ehtch
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deserthee the operetten of the facility and any mejor esfety-related estatessace.
B.
Reportehle Occorrences
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_Reportehle eccentrences, teclesdik correettwo actless and seeeeres to protest recorreece, shall be i
Supplemental reporte any be regestred to folly deserthe fleel reeelet ten of
reported to the IIRC.
la case of corrected er empplenestal reporte, a lleemose evoet report shall be completed,
occurrence, Eveste levolvius systeme et componente and reference shall be made to the original report date.3/4.8.C. 3/4.9.F. 3/4.8.C. 3/4.S.W, 3/4.8.I. 3/4.8.N
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descrlhed In Sectione 3/4.8.B.
l 3/4.9.E. Table 3.9.1-mete 5, Tshle 3.9.2 mete 7. med 3/4.13 de est registre reportise mader the Such evente mill he reported se registred in Sectica 6.7.C.2 er 6.7.C.3 as f
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previelen of thte sect tea.The reporttaa prowletene of thte sectima are set applicable to Sectione 3/4.S.A.
l indleated heles.
j 3/4.5.9, 3/4.8.E. 3/4.8.N, 1/4.9.A. med 3/4.9.s.
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1/ Thie, tabuletinn supplesenta the requiresente of 20.407 ef 10Cpt Pert
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1.
Freest NotiftestIse Wtth Weittse FeIles-5p
= t,,es.f.veste si.t.d bei-.heit he rap.rt.d
.e,editt.o.ir.e,
ibi. het wtue a
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beers by telephone and confirmed by telegraph. estigree, er facelette treeselostas to 4 Strector of the appropriate Besteest Of fice, or his deelseste, es later thee the first 'mastieg l
day fellestas the event, with a erittee fetteer ap report withis two unehe, h erittee fetteer up
report shall teclude, se a stateue a completed copy of a Itceasse evoet report foss.
Internettee provided es the licensee event report fase shall he supplemented, se needed, by l
addittemet estrative materiet to prevl,de complete espleesttee of the circemeteaces serremed(se o
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the eveet.
I Fettere of the Beacter Fretecties System er other eyetene esbject to limiting eefety system e.
settless to lettiste the regelred protective foncties by the ties a asettered parameter reaches the setpelet specified as the tiettisa eefety eyetse settles la the Technical speelficattene er tettere to complete the regelred protective feeettee.
i Note: Isotrument drif t discovered as a result of teetles need est he reported ender thie l
it.e het me, he r.,ertshie med.c itene 1.e. 1.f.c 2.. hel.
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Operettee of the sett er af fected eyetens when say parameter er operettee sebject to a
Itettles condittee le lose ceaservettve thee the least coseervettve aspect of the tiettles l
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condittee for operettee estehltehed to the Techetcal Spectiteettees.
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Note: If specified acties to tekee shoe a system to famed to be operettes hetenee the oest conservettve end the least conservettve aspects of a llettles coedities for operettee iteted to the Techetcal Spectiteettoes, the Itettles condittee for operettee to set comeldered to have been violated and esed set he reported under
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f this ites, but it may be reportehle under Item 2.b below.
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Aheeruel degradattom discovered to feel claddf ag, reacter coole et presente hemedary or
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primary containeest.
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Notes Leakage of valve peckles or gaskete withte the llette for ideettfled leakage set forth to Techetcal Specificettees osed eet he reported' oeder this Stee.
i 210
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d.
Reactivity seemettee. levolvies disagreseest with the peedteced geles of reestivity belsace moder steady-etete ceedittees duties power operettee, greater thee or egnet to II k/kg a
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calculated reactivity heleece tedicaties a stestdese eerste less conservettve thee epocitted to the Tact.atcal Specif 8cattees; ehert-tese reactivity tecrosses timet correepeed to a reacter perled of lese thee S seceede er of emberttleal, se empleased reactlgtty tenerties of more thee 0.51 Ak/k or accorrence of any mapleased criticality.
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yattere er selfunctles of een er more campeesets wentch proveets or could pengest, by i
s.
itself, the fetittleest of the tenettemel reestremente of systee(s) used to cope with l
accidente analysed le the SAR.
f.
Perseemet error er precedural teedeguacy s4mich prevoete er caste proveet, by itself, the I
felf ttleent of the fumettenel requiremento of systees required to cope with accidente analysed la the SAR.
tiete s yer Itene 1.s med 1.f. reduced redeedency that does est reeelt le e lose of system (
functies need met he reported under thle sectice het any be reportehle seder itsee j
2.h and 2.c helow.
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Ceedittene artetes f rom seteral er maa-mode evente that, as e direct reemit of the seest.
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require Fleet ehetdome, operettee of estety systems, er other protective measures regelred j
by Technical Spectftcatione.
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Errere diocevered to the treesteet er steidest anslyees or to the methode used for each l
emelyses es descrthed to the safety analyele report er to the bases for the Techetcal
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Specificattene that have er could have permitted reacter operettee la e esoner lese
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conservative thee seaweed to the seatyees.
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yerformance of structures, eyotene er campeeente that regattee remediet actice er l
corrective seasures to provost operettee to a meneer less coseervettve then esessed to the i
acetdent anstyees to the saf ety amelyste report er Techetcal Specifiesttees beoes; er (
diocevery dertes pleet life of condittees met specitteetly comeldered to the safety l
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analyste report er Techetcal Specificatlees that reptre remedtst actice er corrective
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sesoures to prevent the suj etence of develope,es : et se emeale condittee.
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Note: Thie Itee to inteMed to provide for reportins of potenttally gemerte problees.
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2LI Od Amendeent No.
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2.
Thirty Boy Weltten Reports The reportable occurrences discussed below shall be the subject of writtee reports to the Yte Strector of the appropriate Resteest Office withis 30 doye of accorrence of the evoet.s foss.
urtttee report shell loclude, se a eteleue, e esopleted copy of a liceeses ewe dtog additteest secrettve esterial to provide complete empleestion of the etreuestances surreme the event.
Beector Protection Systes er eagf eeered eefety feature toetrument settlage whteh are found hich de to he lees conservet two them these esteillahed by the Techetcal Specificettene but w e.
of the functiemel requiremente of ef fected eyotees.
met prewest clie fulfilleent Ceedittene leedtag to operettee le e degraded ende perettted by a llettlag condittee for shutdown required by a llettise condities for operettee.
b.
operettee er plaat
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j Eeuttee survet tlance teettag, f eetrument celthrotten er preventattwo estateneocehe which require systes configurettene se described in itsee 2.e end 2.b esed met Note
reported encept where' test resulte theseelves reweel e desseded made es described ebeve.
- Observed Imedequecies la the Septementattee of edeletetrative er procedural centrole which Systeme threates to cause reduettee of degree of redwedency provided to Beector Protecties
,
c.
or Esgineered Saf ety Feature Systees.
Absormal degradettee of systees other thee these specified to 1tes 2.c above deelseed to d.
contate redleact two matertal resulttog f ree the fleelen procene.
Emekage of Sealed eeurces er celthrotten sources are met feeluded ender thle Stee.
valve pechlag er seekete withis the Isotte for identitled teenage set forth to Note:
Techalcol Speelf tcettoes need met be reported under thf e Stee.
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o 717 I
Amendeest No.
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Untene Reporties Regetremente 1.
Sentecomet Effluent gelease Report a.
Within 60 days af ter Jammary 1 and July 1 of each year, a report shall be
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covertog the radioactive content of af fluente teleased to warestricted areas dayles the l
prevtees ela monthe of operation.
I
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b.
The radioactive ef fluent release reporte shall inc1ede a semeery of the gesetitles of i
radteactive 1tgeld and gaseems affluente and seltd weete reteseed trea the emit se outilmed l
in Regulatory cuide 1.21, Reviates 1, June 1974, "Messerlag, Evatnettag and Reporting j
Radioactivity in Setid Waetse and Releases of Radteactive Noterlate la Ligold and Ceeeene l
Ef fluente f rom Light-Water-cooled IInclear power plante", with data senserland es a j
guarterly beste followleg the format of Appeedts B thereof. Per sette mestes the format i
for Table 3 in Appendia B of Regulatory Gelde 1.21 abatt he supplemented with three l
edditional categertees clase of solid wastes (se defteed by 10Cpt part 61), type of l
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coetainer (e.g., LSA, Type A, Type B, large quantity), and seltdtiteetten agent er abeerbent, if any.
l In additten, the radioactive effleest release report to be sekoitted 60 days af ter Jameery l
1 of each year shall include an annual summary of beerly esteerelegical data cettected ever j
the prerflous year. This enamel summary eey be either to the form of as heer-by-hour
l 18eting on magnette tape of wind speed, wtad directies, atesopherte etablitty, and practpitation (if measured), or to the form of joint fregeoecy distributtene of teind speed, wind direction, and atpaspheric stablitty.* This ease report (or a supplement to it to be omheitted within 180 days of January 1 each year) ebe11 teclude se secesoment of the radiation dosee due to the redteactive 11 geld and gaseems ef fleesta roleesed f rom the mett during the previous calender year. (The sentennual effluent release report owheitted within 60 days of July 1 each year need est contata any deee eettestee f rom the prewteen 6 months' effluent releases.) The ef fluent reported eekoitted af ter Jennery 1 each year shall eleo include an assessment of the radietten doses f ree radioactive ef fluente to l
- In lieu of subeteston with the first half year radteactive effluent release report, the licensee bee the optione of retelning thte ouemary of required meteorological data in a file that eheti be provided to the NRC upon request.
Aegadeent No.
211
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member (s) of the pubite due to esy allowed recreettemet activities Emelde the ette hemedary dettag the prevlees esteeder year. All assumptione used to makter thee seessemente (e.g.,
For any specific activity, espesure time and lecetten) ohell be testeded to these reporte.
botch er discrete see ve1 wee retenees, the meteorotegical condittees concorrent with the eles of release of radleective esterials to geseems ef fleeste (as deteratead by ag&tas For frequency and mesesrement) ehall be need for detereintes the gessome patheer deege.
radioactive esteriole reteneed to contineens ef fluent etresse, quarterly everage meteerstestcal corsittoes concurrent eith the quarterly roleses perted ehett be used for detereistas the geveone pathesy desee. The assessment of rediettee deoes shall be perfereed in accordance eith the Of f-ttte Bees Calculetten Ideemet (0000).
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Utth the itette of Specificetten 3.8.08.1 botes escoeded dettes the caleeder year, the i
radioective af flueet rolesse report to be embattted 60 days af ter Jeemary 1 et each year shall stee include se seeesoment of radiatten deoes to the Itkely seet esposed rest
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member (s) of the public f ree reacter rolesees (tectedtes deoes f ree primary effleest
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pathesys and direct radletten) for the prewtees caleeder year to show conferesace with 40CFt190. Enviresumental Radietten Fratecties Standards for Nuclear Peeer Operettee.
j j
The radioactive effluent release reporte ebe11 teclude e itet and description of emplesned l
l retenees f ree the ette to atte boundary of radioactive meterlate to gaseems and itquid ef fluente made during the reporting perted.
j With the quantity of radteactive material to any estelde task escoedtes the 1tatt of
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Spectf tcation 3.8.D.1 describe the evente Reedles to this condittee to the sent i
Radteactive Effluent Eglease Report.
l If toeperable radioactive 11 geld offleest menttertag teatromentatten to set rotermed te
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operable statue prior to the next release purement to liete 4 et Tehte 3.9.1. explate in the
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east Radteactive Ef fluent Release Report the ressee(s) for delay to correcties the inoperaktitty.
If toeperable geoeous ef fluent mootterleg instrumentattee to set rotermed to,eperable to Note 5 of Table 3.9.2. esplate to the east Radioactive l
status eithin 30 days pursueet the reason (e) for delay in correcting the toeperability, j
Effluent Release Report i
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214 Amendment No.
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TTNFS With milk samples no leeger avatlable f ree see er more of the esepts tesettees required by Table 3.9.3. Identify the cause(s) of the sample (s) ne toeger botas evettable, identify the new location (s) for obtstelas available repiecesent seaples, sed teclude revised 0D06
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figure (s) and table (s) reflecting the new locattoe(s) is the mest Redteactive 58flueet
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Release Report.
With a land use census identifyles see er more locattees which yield at least a 20 percent greater dose or dose commitment than the values currently botas calculated to Specificaties
j 4.8.C.1, identif y the new location (s) le the mest Radteactive Effloset Release Report.
>
Changes made dertog the reporttaa period to the Process Control Fregren (FCP) and to the I
Off-Site Dose Calculotten Manuel (ODQt), shall be identified to the esat Radioactive l
Efflueet Release Report.
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Special Reporte Speclet reporte shall be outettted to the Director of the Office of Isopectice and Referceeest
I Bestenel Office within the Line period specified for each report.
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Liquid Effluente, spectricettene 3.8.5 and 3.S.C.
s.
With the calculated dose f rom the release of redteactive esterlate le 11guld affluente
,
l exceeding any of the tiette of Specificaties 3.8.5.1, propere and outett to the Coastselen within 30 days a special report which identifies the cause(s) for encoedtag the itete(s)
,
j and defines the correcstve actions tahms to assure that embeequent rolesses will be in l
compliance with the tiette of Spectficaties 3.8.8.1.
With liquid radweste being discharged without procesetag threegh appropriate treatment eystems and eettested dosee la excede of Specificattos 3.0.C.1, prepara and euhett to the Cometesten within 30 days a apecial report which tecludes the fellevtes teformation:
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esplanetten of why 11guld redweste wee betes discharged without treatment.
(1)
i identification of any inoperable equipment er embeyetese, and the rea' sons for the
inoperabtiItyi 215
Ame ndment No.
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(2)
action (s) taken to restore the inoperable egetpeent to operable stetmas and (3)
Seenery description of action (s) takes to prevent a recorrence.
h.
Geseene ef fluente Specificattees 3.8.F. 3.8.0, 3.0.5, and 3.8.1.
With the calculated att dose free radioactive sable gemee is gemeene ef fleeste escoedtag
any of the limite of Specificaties 3.8.F.1, propero and embett to the Comaleeten withtm 30
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day's a spectet report uhtch idestifies the cause(s) for escoedtog the liett(s) med the corrective action (s) taken to essere that scheogeest releases wit! he la esepitence with the liette of Specificatten 3.8.F.1.
With the calculated does from the release of ledine-131, ledine-133, trities, and/or,redteamelides la portteelete fers escoedies any of the limite of Specification 3.8.0.1, prepara ord estett to the Ceanteelee within 30 days a special report which identif tee the casee(s) for escoeding the itett(s) and the corrective action (e) taken to sesere that enkeequent releases will be is compliance with the tiette of
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Specification 3.8.C.I.
With gaseems redweste hates discharged without preconstes threagh appropriate treatment systees se defined in Specificatten 3.8.M.1 for more than saves (7) consecutive days, or la excese of the limite of Specificatten 3.8.1.I, prepare and enheit to the Cemeteeten within
30 days a special report which lectedes the followles leformattee (1)
explanetten of why saaeems redweste wee being discharged withmet treateset (Spectitcation 3.8.M.1), or with resettant desee in escese of Specificatten 3.8.1.1, identtficatten of any ineputu e agetpoesi. or subeystese, erJ the teameos for the
inoperability; (?)
action (s) taken to restore the looperable agelpeent to operable statues and
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(3)
euemary description of actiee(s) takes to prevent a recurrence.
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i Total Dese, Specificaties 3.8.N.
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With the calculated dose free the release of radioactive esteriale le Itquid er geoeems efflosete suceeding the tiette of Specificettee 3.0.N. Propere ord enheit to the Commissies
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withis 30 days a special report which dettees the corrective actiee(s) to be hqgge to i
l vedece subsequent releases to prevent recurreece of escoeding the liette of Spes44teatten This special 3.4.N and tecludes the schedule for achieving coeformance with these 11ette.
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report, required by 10CFE Part 20.405e, shall include se analyets that settentes the radiaties esposure (dese) to a eseber of the public free stettes eserces, testedtes att l
ef flueet pathueye and direct radiettee, for the talender year that lectedes the rolesee(s)
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It ehell alas describe levele of radiattee and coecostrations of l
covered by this report.
If f
redteactive materiet invet,ved, and the cause of the espesure levele er coecentrattene.
the entiested deses exceed any of the llette of Specificatten 3.8.N. and if the release
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j condittee resulttog is violattee of 40CFR Part 190 has met already hoes corrected, the l
special report shall include a request for a vertence is accordance with the provielene of Subetttal of the report le ceneidered a timely request, and a variance is i
40CFR Fort 190.
l granted setti etaff action on the request to complete.
Radielegical Enviressental Nemitories. Spectiteetion 3.9.C.
d.
With the level of radioactivity se the result of pleet effleeste le se envirosasetal sempiles media at see er more of the Recettene specified in Table 3.9.3 exceeding the
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reporting levels of Table 3.9.4, prepare end embait to the Counteeton within 30 dare free the recetyt of the 1.aboratory Aestyees a special report which tecludes se evaluatise of any
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f Table
, release conditione, enviyonneetal facters or other f actere which coneed the liette o 3.9.4 to be exceeded. This report le set reqetred if the esseered level of radioactivity was not the result of plast efflesets. heuever, le such se evoet, the coaditten shall be -
reported and deserthed is the annual Radiological Revireemental Servet11ance Report.
Lead Use census. Specificatten 3.9.D.
e.
With a land use census not being coeducted as required by Specificettee 3.9.9,, prepare and submit to the Cometeelen within 30 days a special report which identif tes the reasons why the survey use not conducted, and what steps are being takes to correct the ettuettoa.
I 217 Aseedment'No.
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Revirossental Radletealcel b etteries
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Sediological Revitenmental Servettlance Reporte coverlag the operettee of the melt prog $ges salender year shall be sehnitted prior to Ney 1 et each year.
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1 The seesen Radielegical Revireemental Servet11ance Report shalt teelude sammeries.
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interpretettoes, and as analysis of trende of the resente of the redtelegtest envissemental servet11eace activities for the report perled, includies a campertees with operetteest centrole (se appropriate), and prewtees envireemental servettlance reporte and se seeeeeeeet of the observed tapacte of the plant operaties en the envireement.
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l The seemet Radielegical Reviremmental Servet11asee Report shall toelade commerland and tehulated
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resette of all redtelegical envareneestal samples tekee derias the report perled peroneet to the
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table and itseres le the 0000. le the event that eene recette are met avettable for lectueles i
i mith the report, the report shall be enheitted nettaa med emplaintes the ressees for the misstag
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reemite. The misetas data shall be embattted as seen se poselble is a sepplementary report.
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Wtth the level ef redtoectivity ie se envireementat semplias media et one or more of ahe locattene specified to Table 3.9.3 eseeedias the reportiss levele of Table 3.9.4. the condities
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ehall be deserthed in the next seenal Radiotegical Revironmental Servet11amme Report eely if the meneered level of redleectivity use est the reemit of pleet efflemets. With the radiologicat
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emetressental meettering progree not helas condected se specified to Table 3.9.3. a descripttee of the reasone for not conductims the progree se regelred and the pleae for proveetles a
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i recurrence shall be incleded to the next seemet Bedtelegical Enviressental Servettlance Report.
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The seneal Radtelegical Restressental Servet11mece Report ehelt stee Seelade the resente of the l
1ead use comeus regetred by Spectiteetion 3.9.9 A sammary descripttee of the redtelestcal l
emetroenestal semitertas progree lectedtag a esp of att samp11ag lacettene hayed to a table giving dietences and directions free the reacter obe11 he to the reporte. If use oevironnestal sempting locations are identified le accordance ettk Specificaties 3.9.B. the new lacettees shall
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he identified to the next enmeet Radiotegical Revironeestal Surveillance Report.
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l The reporte shall slee include a discueeles of att analysee in which the 1.L5 required by Table 4.9.3 use not achievable.
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f The resulte of Itcensee participattee le the intercomparteen program regelsed by With emetyees est hates perfeemed as Specification 3.9.5 shell be tecluded to the reporte.
l regelred by Spectiteetten 3.9.5, the corrective actione takes to prevent a recorrence steelt be
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r. pert t. t_t..t.e to t
.t._.1 E tet tc.1.evire_.t..
tv.111_. g,
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f 6.4 Fire Protectice Inspectice As ledereedest fire protectlee and leen preventies Respecties and medit shall be perfereed seenstly
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ot111stes either qualif ted of f stte itceasee perseenet er se outside fire protection fire.
j A.
As tospection and audit by se outside fire ceasettent shall be performed at fatervete es greater then
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l 3 years.
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6.9 Reviconsentat OsaltfIcetien A.
By se later then June 30, 1982, all safety-related electrical equipeset to the factitty shell he
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valuating Enviteesental quattf tcettee of Ctese 18 Electrical Equiposet to Operettes teactere" (30E
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Guldettese)g er W asG-0588, "leterte Staff Feettles se Revitessestal geettittattee of Safety-Related l
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Electrical Egetpeent*, Decesher 1979. Copies of these documente are attached to order for
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Modificettee of License DPR-28, dated Seteber 24, 1980.
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By se later then Decesher 1,1980, esoplete and meditehle recorde aset be asettable end estetsteed at I
a costrel locettee which describe the emetreneestal qualificettee mothed used for all eefety-related E.
to suffletent detall to document the degree of campitence with the 908 Guidellees I
electrical equipment to Thereaf ter, such recorde should be updated and meisteleed correst as egetposet er W EEG-05SS.
replaced, further tested, or otherwise qualif ted.
6.10 totearity of Byetene outside Containeemt
& progree to reduce leakage free ersteme outelde costelmeest that would er coeld contate highly redteactive
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This fluide ductsq a serieve treesteet er accident to se les as practical levele will he implemented.
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i progree shall lectode the foltoutng l
219 Amendment No, d3
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l Pregteteos estabitehing preventive seleteneece and perledic visual leopectice regelsemeets.
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Systes leakage toepectione, to the esteet permitted by eyeten deelse med redtelegical seedittees, for
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each erstes et a f regeency met to esceed refeating cycle totervale.(1) Reeldwel Meet R The eyetene embject to a e i
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l testing eres (5) actc, med (6) sempites systees.
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l 6.11 ledtse Meettering f
A progree which will ensure the capahtlity to accurately deterates the ettberes tedies caecentrattee to vitet erese* moder accident condittees will be taptemented. This progree ehe11 teclude the followings l
h A.
Tretning of perseasel.
5.
Precedures for mentteries.
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Previstoms for estatessace of esepites and aestyete equiposet.
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6.12 Frecess Centret Prearse (PCF)
A procese contret progree shall contate the seepitas, seelyste, teste, and deterstaattees by which wet
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redteactive weste free Itquid systees to escured to be converted to e fore settable for off-site disposal.
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Licensee lettleted changes to the PCF:
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Shalt be subettted to the come(esten to the seateemmet Efflueet gelease Report for the period to l
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i which the change (s) was mode. Yhte embatttet shall centstas
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Suf ficiently detailed teformattee to support the rettoeste for the change withmet benefit l
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of oddittoest er supplementet teformatten.
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- Areas requiring personeet access for estabitehteg hot shutdove condittee.
l 220 Ameedoest No. M3
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i A determinetten that the change did not reduce the overall comformeene of the dauntered l
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opent restne/fliter media weste product to estetlag criterte for eeltd weste shipmente and dispoest.
Documentatten of the fact that the change bias been reviewed by p0EC and by the c.
Manager of Operations (N00).
Shall haceae ef fective open review by regC and approval by the IIsenger of operettene (moo).
2.
6.13 Of f-Site Bees' Caleetetten Manual (ODOI)
An Off-Site Bose Calculation Mempel shall contata the current methodelegy and peranstere used in the calcatettom of off site doses due to radteactive gaseems and tigeld effluente, to the cancelation of gemeene and 11 geld ef fluent monitoring alare/ trip setpointe, and in the conduct of the environmental
. radiological monitoring program.
A.
Licensee lattleted changes to the G000:
Shall be submitted to the Cnentesten in the sente:.noni. affleeset Bolesee Report for the perted in 1.
which the change (s) was mad ef fective. This sobe tttal shall coetain
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Suf fletently dotatted Reformatten to support the rettemete for the cheese withest bene,f te
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of additional er espplemental informatten. Informattee omheitted should comelet of a pachase of those pages of the 000t to be changed with each page numbered and provided with an approval and date gou, together with appropriate smalysee er evaluettens joettfying the c hange( s).
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A determinetton that the change will not reduce the accuracy or rentability of dose b.
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calculations or setpoint deterstentiene.
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Documentation of the f act that the change hee been reviewed by regC and approved by the
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Manager of Operattone (M00).
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Shell become ef fective upon review by regC and approved by the Manager of Operations (M00).
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221
Amendment No.
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6.14 neler Cheesee to Radteactive Lieeld, caseeve. and Solid Weste Treatenet Sveteme I
d seitd):
l Licessee-lettleted gejor cheesee to the radioactive unste erstees (Itgeld, geoeems, se
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Seport Shell he reported to the Coasteeles in' the seatseenal Radleestive Effleest Seleses en The dioceselee of each eheese perled in which the eveneettee was reviewed by the retC.
A.
A semeery of the eyeleetles that led to the deteraleottee that the cheese could be made
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secordesca with 10CFR Part 50.593 Suffteleet detailed informaties to empport the resses for the cheese withmet beenfit of
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addittomet er supplementet informatten; f
A detailed descripties of the egelpment, camponente, med processes tevolved and the 1 st f
3.
with other pleet synteses in
&e evateottee of the cheese, which shows the predicted rol
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4.
- predicted in the license oppilcettee and amendeeete theretog
( ) of the As evoleottee of the cheese. which shove the napected easteen esposerse to seeker e
h previemely puhtic et the site beendary and to the generet pepelottee that differ free t ese S.
l eetlested to the iteesse appitcottee and seeeeeeets theretog fflosete A couperleen of the predicted" rolesses of radiesetive meteriale. to Itgeld and geneese e
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h h ses are to he med in solid weste, to the actual roleseos for the perted prior to when t e c ee 6.
medes An eetleate of the espesure to pleet operettes peroommel as a result of the cheesel and
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C Documentattee of the fact that the cheese wee reviewed and found acceptable by POS.
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.heni haceae of f-ttve e,ee r.wi.e med occa,te-e hr c and e,,r..e1 by the nest neeeger.
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Specificettee se part of the sneest FSAR opdate.
_.* Licensee any cheoes to outett the teformaties called for la thte I
222
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Amendeest No.
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I Attachment 2 SIGNIFICANT CHANGES TO THE ANSWER KEY The following changes represent only those facility comments that resulted in significant changes to the answee key or were not resolved during the exam review.
Insignificant changes, i.e.: Typo's, minor set point changes, are reflected in the master answer key.
Question #
5.02 Eliminated reference to "no excessive over pressure occurs".
6.02 Correct isolation groups listed as starting on 82.5" level and include pressure permissives.
7.12 The first part of this answer is not stated in the reference listed.
It only addresses the concerns about the mechanical vacuum pump.
Scratch everything up to the mechanical vacuum pump.
8.01 In grading consider that an LPRM exchange is not considered a core alteration at Vermont Yankee.
C NRC Resolution 5.02 Comment accepted 6.02 Comment accepted 7.12 Considered during grading 8.01 Considered during grading