ML20151U400
| ML20151U400 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/28/1988 |
| From: | Drawbridge B YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20151R758 | List: |
| References | |
| TR-88-225.5.2, NUDOCS 8808190071 | |
| Download: ML20151U400 (8) | |
Text
F]rnehmed b YANKEE ATOMIC ELECTRIC COMPANY r.i.non. m m m e,
,, en Star Route, Rcwe, Massachusetts 01367 3p1,f
.YAN KEE m.
June 28, 1988 TR-88-225.5.2 Regional Administrator Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Dear Sir:
On June 22, 1988, an SRO Written Examination was administered at Yankee Nuclear Power Station in Rowe. During a review of the exam by facility personnel, five (5) questions / answers were identified as needing additional input or change. It is requested that the comments on these five (5) questions be given due consideration for inclusion prior to the grading process. The five (5) questions, attached, are #5.05, 6.02, 6.04, 6.08, and 8.02.
If additional information is needed, please contact Russ Clark, Training Manager. Thank you for your cooperation.
Since g l
.c %
Bruce L. Draw Vice President /
Manager of Operations DHW/maf Attachments (1-5) cc:
E. Yachmiak, NRC F. Jagger, EG&G N. St. Laurent, YNPS T. K. Henderson, YNPS C. R. Clark, YNPS G. Papanic, YAEC o
8808190071 080806 PDR ADOCK 05000029 I
V PDR I
ATTACHMENT 1 A.
Question 5.05 (1.00)
Following a reactor trip.from two weeks of 100 percent power operation, xenon concentration will peak in approximately how many hours?
Answer 5.05 (1.00) 8.5 (+/- 1.0). [1.00)
YNPS Rx Physics Trg Manual, Ch 18, Section:
"Xenon Facts."
YNPS Rx Physics Trg Manual, Ch 18, Obj:
"Learn the xenon facts concerning plant operation."
m B.
Comment - YNPS Rx Physics Trg Manual is in draft form and is being edited to be consistent with other supporting training material. The Data Reference Manual, controlled copy, is used for actual information and the YNPS Rx Physics Trg Manual will reflect this.
Change answer to 7.0 (+/-1.0)
C.
Ref.
Data Reference Manual, Pg C-9 t
h
m.-. -
ATTACHMENT 2 i
A.
Question 6.02 (1.50)
What are the six (6) uses for the information supplied by
)
the Incore Thermocouple and Reference Jenetion Box RTDs?
Answer 1) digital indication on the MCB 2) subcoded margin monitor 3) thermocouple recorders
- 4) portable refueling channel 5)
SPDS 6) safe shutdown system indication YNPS STM Ch 32, Section 4.3 B.
Comment - Question asks for uses yet answer provides inputs.
Operating and Emergency Procedures frequently reference the T/C's, for example:
1) accident identification (Inadequate Core Cooling) OP-3053
- 2) determine cooldown rate during plant cooldown OP-2105
- 3) plant cooldown from Safe Shutdown System OP-3018
- 4) determine margin to saturation OP-3054
- 5) natural circulation OP-3054
- 6) cladding failure OP-3053
- 7) core cooling OP-3053 It is requested that the above also be accepted for full credit.
C.
Ref. As stated above I
h
e ATTACHMENT 3 A.
Question 6.04 (1.75)
A reactor startup.is in progress with power at 10 E-7 amps when the #3 Intermediate Range Channel fails Low.
State the effect this will have on EACH of the TWO (2) source range channels, including the Magnitude of the effect and the REASON for the effect. ALSO, state any alarms which will be generated.
SETPOINTS are required.
Answer 6.04 (1.75)
Source range #2 will remain deenergized (no effect) [0.25]
Source range #1 will energize [0.25] and peg high [0.25] because e
it is interlocked to energize [0.25] when IR #3 drops below 5 X 10~9 amps [0.25]
High SUR alarm signal will be generated [0.25] at 1.0 DPM [0.25]
YNPS STM Ch 33, pg 33 YNPS STM Ch 31, pg 14, 19, 32-34 B.
Comment - 1.0 DPM is the SUR alarm setpoint given by the Systems Training Manual (STM).
This is set by I&C and can vary from calibration to calibration. The Tech Spec setpoint is < 1.1 DPM and does not vary.
Since students are taught both setpoints it is requested that either both be acceptable for credit or.a tolerance be allowed for STM setpoints.
C.
Ref. Tech Specs Table 3.3-1 pg 3/4.3-4
i P'
ATTACHMENT 4
.s A.
Question 6.08 (1.00)
What condition (parameter and setpoint) will cause a DIVERSE PARAMETER (partial) Vapor Container Isolation Actuation System (VCIAS) to actuate?
Answer 6.08 (1.00)
MCS pressure (0.50) < 1650 psig (0.50] (safety injection)
YNPS STM Ch 25, pages 23-24 Handout for Lesson Plan 1/103 m
B.
Comment - Question asks for "condition" (singular), 5 psi in VC is also a correct response.
C.
Ref. YNPS STM Ch 19, pg 134, Figure 19-40
e ATTACEMENT 5 j
'e A
Question 8.02 (1.75) 1 Jiven attachmen: 3, answer the following:
a.
Operation at points at or below any of the curves ensures WHAT TWO (2) conditions DO NOT OCCUR?
(1.00) b.
WHAT Technical Specification action must be taken whenever Main Coolant System (MCS) pressure exceeds 2735 psig?
(0.75)
Answer b.
be in HOT STANDBY [0.25] with MCS pressure reduced to within its limit (0.25] within one hour (0.25]
T.S. page 2-1 B.
Coament - Answer b addresses only Modes 1 and 2.
Answer should reflect Modes 3, 4, 5 also.
Modes 3, 4, 5 - Whenever the MCS pressure has exceeded 2735 psig, reduce the MCS pressure to within its limits within 5 minutes.
Either answer should be acceptable dependent upon initial assumptions.
C.
Ref. YNPS Tech Specs 2.1 pg 2-1 l
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ATTACMMEllT 3 i
'e NRC RESOLUTION OF FACILITY COMMENTS FOR THE YANKEE ROWE SENIOR REACTOR OPERATOR EXAMINATION ADMINISTERED ON JUNE, 22, 1988
.r
, Question Number:
5.05 Focility Comment:
YNPG Rx Physics Trg Manual is in draft form and is being edited to be consistent with other supporting training material.
The Data Reference Manual, controlled copy, is used for actual information and the YNPS RX Physics Trng Manual will reflect this.
Change answer to 7.0 (+/-l.0)
NRC Resolution:
Agree with comment.
Answer key changed to reflect more correct answer.
Additional answer added to key.
Question Number:
6.02 Facility Comment:
Question asks for uses yet answer provides inputs.
Operating and Emergency Procedures frequently reference the T/C's, for example:
1) accident identification (Inadequate coe cooling) 2)
determine cooldown rate during plant cooldown 3) plant cooldown from Safe Shutdown System 4) determine margin to saturation 5) natural circulation 6) cladding failure 7) core cooling It is requested that the above also be accepted for full credit.
NRC Resolution:
Agree with comment.
Additional correct answers added to answer key.
Question Number:
6.04 Facility Comment:
1.0 DPM is the SUR alarm setpoint given by the Systems Training Manual (STM).
This is set by I&C and can vary
{
from calibration to calibration.
The Tech Spec setpoint is </= 1.1 DPH and does not vary.
Since students are taught both setpoints it is requested that either both be acceptable for credit or a tolerance be allowed for STM setpoints.
NRC Resolution:
Agree with comment.
Answer key will be changed to accept either answer.
3 47.,
( Qusation Numbar:
6.08 l
f(
Facility Comment:
Question asks for "condition" (singular), 5 psi in VC is also a correct response.
NRC Resolution:
Agree with comment.
Answer key will be changed to accept "5 psi in VC" as an additional correct response, j
Question Number:
8.02 Fccility Comment:
Answer b addresses only Modes 1 and 2.
Answer should reflect Modes 3, 4,,5 also.
Modes 3, 4,
5 - Whenever the MCS pressure has exceeded 2735 psig, reduce the MCS pressure to within its limits within 5 minutes.
Either answer should be acceptable dependent upon initial assumptions.
NRC Resolution:
Agree with comment.
Answer key will be changed to require actions for all 5 modes of operation.
All modes are required since question asks...whenever MCS pressure exceeds 2735 psig.
ADDITIONAL CHANGES MADE BY GRADER:
Question Number:
5.07 Changed distribution of point values to better reflect ellicited information.
Question Number:
5.11 Changed distribution of point values to better reflect ellicited information.
Question Number:
8.15 l
Added "(Temporary Change)" to the Jumper and Lifted Lead Log to reflect common nomenclature of the log.
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