ML19353A976
| ML19353A976 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/28/1989 |
| From: | Burdick T, Reidinger T, Shembarger K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19353A975 | List: |
| References | |
| 50-456-OL-89-02, 50-456-OL-89-2, NUDOCS 8912080185 | |
| Download: ML19353A976 (9) | |
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l U.S. NUCLEAR REGULATORY COMMISSION I
REGION III Report No. 50-456/0L-89-02 Docket No-50-456 License No. NPF-72
' Licensee: Commonwealth Edison Company Post Office Box 767
-1
' Chicago,.IL 60690 j
Facility Name:.Braidwood Station Examination Administered At: Braidwood Station and PTC Simulator Examination Conducted: Week of October 30, 1989 RIII Examiner:
E She&.oa II/99/ff}
K. Shembarger 0 Date Mbb eh I 28$f -
-Chief Examiner:
.T. Reidinger Date Approved By:
M l &~a M b d h /26/D Thomas M. Burdick Date l
Examination Summary Examination administered during the week of October 30, 1989 (Report No. 50-456/-
OL-89-02)):
Consisted of. written and operating examinations administered to two reactor 3
operators and ten senior reactor operators.
Results:
One Senior Reactor Operator failed the written examination.
4 8912000185 8911
{DR ADOCK ' O 56
m REPORT DETAILS 1.
Exit Meeting a.
On November 4, 1989, an exit meeting was held. The following personnel were present at this meeting:
j T. Reidinger - Chief Examiner K. Shembarger - NRC Examiner i
R. Warner - PNL Examiner
-M. Lintz - PNL Examiner R. E. Querio - Braidwood Station Manager G. Vanderheyden - Training Manager D.-0'Brien - Technical Superintendent D. Miller - Regulatory Assurance D. Cooper - Technical Staff Supervisor D. Huston - Training i
b.
1)
One generic weakness relating to fuel handling equipment and
. operation was discussed by the chief examiner with the
- utility, i
2)
One generic weakness was Question No. 28 - Section 6 on the i
SR0 written examination.
Postulating a feed flow transmitter failed low, the question elicited the effects on steam flow, feed flow and S/G 1evel. Eighty-nine (89%) percent of the SR0's failed this question.
c.
The chief examiner discussed that in general the candidates exhibited good training and knowledge in all procedures utilized during the l
examination (operating, abnormal and emergency) and in technical specifications action statements, surveillances and bases. The j
operators exhibited good diagnostic skills,in evaluating precursors relat ng to i:npending degradations of instruments, components and eventt.
l The operators evaluated all GSEP classifications as an integrated crew.
The operators generally exhibited good familiarity with local equipment operations outside the control room.
2.-
NRC Concerns a.
.Braidwood administrative procedure BWAP 340-1 Rev. 5 addresses the requirement that all operators that manipulate valve or equipment per a step with a # sign will manually input that change into the Equipment Status display system (ESD). The ESD is a non-functional l
system at Braidwood.
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b.
The B train auxiliary feed pump diesel will not automatically start on a Safety Injection signal when its breaker is not matched with g
its target, e.g. if the breaker target flag is red vice green in the automatic start switch position the Diesel will not automatically start with a valid SI start signal.
c.
Braidwood abnormal procedure " Low Water Level in the Kankakee River" contains an attachment that requires a Braidwood computer terminal to access the Army Corp of Engineers data for Kankakee river guage heights. Braidwood does not have a dedicated computer for this attachment and the Army Corp of Engineer's computer is out of service.
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SIMULATOR FACILIT REPORT Facility Licensee:
Commonwealth Edison Company Braidwood Nuclear Power. Station - Unit l' Facility Licensee Docket No.:
50-456-Operating Tests Administered At:
Braidwood PTC simulator During the conduct of'the simulator portion of the operating tests, the following items were observed (if none, so state):
ITEM-DESCRIPTION Component cooling Surge Tank Fills up too rapid during a thermal barrier cooling leak.'
i
'RHR and SI Pumps will not cavitate during cold leg recirculation with suction isolation valves failed shut.
Containment Spray Pumps will not'cavF: ate when the spray additisc tank is empty (0 level) and pumps left running for 15 minutes.
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NRC RESOLUTIONS - SR0 EXAMINATION CATEGORY 6 QUESTION: 31 (1.00)
Unit 1 was in mode 5.
S/G's were drained.
lA and~lB AFW pumps were tagged 0.0.S.. When maintenance was draining the 1B AFW pump suction piping, the 1B AFW pump suction valves (lAF006B, AF00178) automatically opened.
What caused the AFW pump suction valves to open?
(INCLUDE ANY LOGIC, COINCIDENCE AND SETPOINT-IF APPLICABLE)
ANSWER: 31 (1.00)
Low suction pressure OR-(14.1 plus or minus 1 psia) (.50) with 2/4 (.125)
S/G's low-low level on 1/4 S/G's OR (40.8%) (3.75)
REFERENCE:
CHAP 26-72, DV 20-1-89-14100, UNIT DIFFERENCES BOOK 061000K402
..(KA's)-
Braidwood Contention::
6.31 Alternate low suction pressure of 1.22 inches Hg should also be accepted.
The AF pressure units were changed in 1988-from inches Hg to psia.
Approximately i of candidates tested were initially trained with the old units, 1.22" Hg is equivalent to 14.1 psia.
REFERENCE:
Braidwood System Description Chapter 26 Rev. 4 NRC RESOLUTION:
Will accept equivalent low suction pressure of 1.22 inches Hg.
- o L. '
e-CATEGORY 5 QUESTION: - (1.00).
While the plant was operating at 75% power, a turbine trip coincident with a
. Pressurizer Pressure Control System malfunction resulted in'an increase in pressurizer pressure to 2745 psig.
(Assume that all other plant systems responded as designed.)
In accordance with Technical Specifications the
- .11nimum requirement is to:
(CHOOSE ONE) a.
within i hour reduce pressure to within its TECH / SPEC limit and be in
. HOT STANDBY.
b.
within 5 minutes reduce pressure to within its TECH / SPEC limit and be in i
HOT STANDBY.
j c.
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reduce' pressure to within its TECH / SPEC limit and be in HOT SHUTDOWN.-
d.
within 5 minutes reduce pressure to within its TECH / SPEC limit and be in HOT SHUTDOWN.
j ANSWER: 03 (1.00) l b
REFERENCE.
4
.I Technical Specification 2.1.2
'000027G003
..(KA's)
-Braidwood Contention:
5.03 This question should be deleted because there is no correct answer. Answer Key lists "b" as the correct choice.
Tech Spec LC0 for exceeding the pressure safety limit in Mode 3 does not mention any action to be taken to place the unit in a lower mode of operation.
l Based on the question, when tha RCS pressure limit was exceeded, the unit should already be in Mode 3.
(Reactor Trip at 2385 psig).
REFERENCE:
Braidwood Technical Specification 2.1.2 REACTOR COOLANT SYSTEM PRESSURE NRC RESOLUTION:
Question deleted
e v y CATEGORY 5 QUESTION: 25 (1.00) l Unit 2 is at 72% power. Rod system control is in automatic. Suddenly the j
turbine has a spurious two rainute runback to 65% power. Shortly after, Tave i
begins to increase above _ Tref. - Tref _ is normal for turbine load.
PZR pressure and level indications are increasing slowly.
Individual rod position indicators indicate no change in any rod positions.
Which ONE of the following is the correct operator response to this situation? (CHOOSE ONE) a.
Place the bank selector switch to manual, and increase turbine load to match Tave to Tref within one degree.
b.
Leave the bank selector switch in automatic and reduce turbine load to l
1ess than 50% within 30 minutes to avoid exceeding axial flux limits.
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c.
Place the bank selector switch to manual and withdraw rods to match Tave to Tref within one degree.
d.
Place the bank selector switch to manual and insert rods to match Tave to Tref.within the rod deadband.
j ANSWER:
25 (1.00)
)
d
REFERENCE:
ROD-2 P2 000005G012
..(KA's) i Braidwood Contention:
5.25 The answer, choice "d", states to " match Tave to Tref within the rod-deadband." This is confusing.
Bw0A ROD-2 states to " match Tave to Tref within i degree." If candidate considered choice "d" to be incorrect, due to the term deadband, then choice "a" is the second choice as a correct statement. Choice "a" is also acceptable per Bw0A ROD-2, RNO column for step 2.
Full credit should be given for either answer "a" or answer "d".
REFERENCE:
Bw0A ROD-2 NRC RESOLUTION::
Question deleted.
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' CATEGORY 6:
. QUESTION: 42 (2.00)
LIST the FOUR responsibilities of the Shift Supervisor when-acting as the Station Director which may NOT be delegated to support personnel.
ANSWER: 42 (2,00) 1.
Classification of the emergency 2.
'The notification of making protective action recommendations (.25)
,to off-site emergency management. agencies (.25)~
.l 3.
Authorization of personnel ex30sure beyond 10 CFR 20 limits 4.
Request assistance from. DOE C11cago Operations Office (0.5 pts each)
REFERENCE:
Bw2P 090-1 KA 4.4-l 194001A116
..(KA's)
Braidwood Contention:
6.42 Answer #1 lists " Classification of the emergency" as one of the four-
- responsibilities that the Station Director cannot delegate. Bw2P 090-1 and i
100-1 both list the " Declaration of the emergency condition," as one of the l
' four responsibilities.that the Station Director cannot delegate.
2 This should be an alternate acceptable answer.
REFERENCE:
BwZP 090-1 and Bw2P 100-1 t
NRC RESOLUTION:
Will accept " Declaration" as an alternative answer L
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NRC RESOLUTION - R0 EXAMINATION CATEGORY 2 QUESTION: 02 (1.00)
One of the emergency Diesel Generators has shutdown due to an overspeed trip (.
1.0)-
WHAT component has to be locally reset before the engine can be restarted?
- ANSWER: 02-(1.00)
(shutdown) butterfly valve (+1.0)
(alternate answer - engine _overspeed trip isolation valve 1DG5109A, B or 2DG5109A, B)
REFERENCE:
1 1.
1Bw0A " Emergency Start of A Diesel Generator - Unit 1".
Attachment B, Rev. 54, 2.
Braidwood System Training Manual Chapter 9 Diesel Generator and Auxiliaries p 9-43.
3.-
KA Numbers 000055A102 (4.3).
j Braidwood Contention:
Air intake damper is an equivalent answer.
NRC RESOLUTION:-
Will accept air' intake damper as alternate answer.
-QUESTION:,17 (1.50)-
WHAT inputs are used by the Subcooling Margin Monitor (SMM) to perform its
~
emergency function in an Inadequate Core Cooling Incident? (1.5)
ANSWER: '17 (1.50) l.
Average (+0.5) of 10 highest CET's (0,5) l RCS Pressure (+0.5) l REFERENCEi l
L 1.
Braidwood Systems Training Manual. Chapter 34B Inadequate Core Cooling System,-p. 34B-41.
2.
KA Numbers 000074A201 (4.6)
Braidwood Contention:
Accept Containment pressure and containment radiation as inputs to SSM.
NRC RESOLUTION:
Will accept containment pressure and containment radiation.