ML20108E027
| ML20108E027 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/10/1984 |
| From: | Boyer V PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| CON-#185-626 OL, NUDOCS 8412140102 | |
| Download: ML20108E027 (20) | |
Text
-.
i PHILADELPHIA ELECTRIC COMPANY-2301 MARKET STREET P.O'. BOX 8699 PHILADELPHIA. PA.19101 (215)841-4500 V. S. BO Y E R sa. vicE rnessocNT December 10, 1984 NUCLE AR POWER Docket No. 50-352 Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.
C.,
20555
Dear Mr. Eisenhut:
This letter provides follow-up information to my letter dated August 21, 1984 concerning updates on the status of Shift Advisors and Shift SLO personnel participating in the 6 weeks of hot participation experience for the Limerick Generating Station Unit No. 1.
In addition, this letter will satisfy the certification requirements of Attachment 3 to Facility Operating License No. NPF-27. of the August 21 letter indicated that written and oral examinations administered to the shift advisors, including test results, would be forwarded when available. of this letter includes a copy of the written examination and the oral examination format administered on Sept 21, 1984 for the shift advisors.
The oral examination included simulator scenarios and a Plant Control Room walkaround.
These oral exams were administered and graded by the LGS Assistant Station Superintendent and the Operations Engineer.
The written exam was a 4-hour exam covering plant systems, procedures, and technical specifications and was administered and graded by the LGS Training Coordinator.
8412140102 841210 PDR ADOCK 05000352 pyg V
Boot it i
DMr. Darrell'G. EisenhutT December 10, 1984 Page 2-
.The examination' grades for the two Shift Advisor
. candidates are1as follows:
~ I.
iMULL EXAMINATION I
Control Room Simulator Walkaround D..H.
Sparks PASS PASS F. L. Shanaman
~ PASS PASS II.
WRITTEN EXAMINATION Section Section Section I
II III' Overall D.-H.' Sparks 77.4 84.5 84.5 82.2' F. L. Shanaman 92.8 83.3 78.9 84.9 r
Records for this Shift Advisor _ Training are-cappropriately documented'and kept by the LGS-Nuclear Training Section.
Based'upon-the foregoing it is hereby certified, in accordance with Attachment 3'to Facility' Operating License NPF--
-27,'that'D.H. Sparks.and'F. L. Shanaman arethe special. assigned advisors and ' they have.been examined and have been determined -tx) be competent to provide advice ~to-the operating shifts.
' Enclosure 2 lists SLO personnel who participated in the Hot Participation. Experience Training (>20% Rx power) for 6 weeks in order to_ supplement their cold' license due to having.no previous " hot" experience..This list does not include Mr.
Charles P. Gillespie who is the only Shift' Superintendent.(SLO)~
designated to have a. Shift Advisor on Shift with him at all times
-when not in Cold Shutdown condition.
Mr.'Gillespie did,'however,
-participate in the 6-week program to help improve his " hot plant" awareness.
Records indicating appropriate documentation of the six weeks of hot participation. experience training for each SLO participant are kept by the LGS-Nuclear Training Section.
r Mr._Darrell G. Eisenhut December 10, 1984-Page 3 If'you have any questions or-require additional
-~
information,-please do not hesitate to contact us.
Very truly'yours, Attachments cc:
Dr. T. E. Murley, Administrator See Attached Service List
i cc: ' Judge Helen F. Hoyt Judge Jerry HarDour l
Judge Richard F. Cole
')
Judge Christine N. Kohl Judge Gary J. Edles
' Judge Reginald L. Gotchy j
Troy B. Conner, Jr., Esq.
j Ann P. Hodgdon, Esq.
- Mr. Frank R.' Romano Mr. Robert L. Anthony Ms. Phyllis Zitzer
~
Charles W. Elliott, Esq.
Zori G. Ferkin, Esq.
Mr. Thomas Gerusky j
i Director, Penna. Emergency Management Agency
-)
Angus Love, Esq.
David Wersan, Esq.
Robert J. Sugarman, Esq.
Martha W. Bush, Esq.
. Spence W. Perry, Esq.
Jay M. Gutierrez, Ecq.
Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section ~ (3 copies)
James Wiggins Timothy R. S. Calopbell 4
t COMMONWEALTH - OF.' PENNSYLVANIA. :
ss.
COUNTY OF PHILADELPHIA-says:.
V. S. Boyer, being first duly sworn, deposes and That he is Senior Vice President ~of
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~ Philadelphia Electric Company; that he has read the' foregoing
-letter +with. respect to shift staffing for Limerick Generating Station Unit No. 1 and knows the contents.thereof; and that the Statements'.and matters _ set forth therein are true and correct to the[best-of his knowledge, information and belief.
Subscribed ~and sworn to
-befor e me this id' day
- of Decemove. 664 J23b4Jf b aS~'
u
.gNotaryPublic JUDITH Y. FRANKUN Notary Public, Phila., Phila. Co.
My Commission Expires July 28,1987
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DATE PASSED Q ADVISOR FAILED Q COMMENTS l
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6.0 REACTIVITY EFFECTS 7.0 ADMINISTRATIVE REQUIREMENTS 5.
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7.2 Facility Requirements COMMENTS: taeeu# red for "u"J s
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4.0 REACTOR PROTECTION a
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4.3 Interlocks 5.9 PROCEDURES g
5.1 Normal Procedures 5.2 Abnormal Procedures 5.3 Emergency Procedures Ibkh k k-hh f
7.0 ADMINISTRATIVE REQUIREMENTS I
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5.1 Normal Procedures 53 Abnormal Proceduree 5.3 Emergency Procedures 7A ADMINISTRATIVE REQUIREMENTS 7.1 Technical Specificationr.
7.2 Facility Requirements COMMENTS: taeoired for "tr?
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LIMERICK GENERATING STATION Shift Advisor Facility:
Limerick Generating Station Reactor Type:
BWR Date Administered:
Examiner:
Applicant:
INSTRUCTIONS TO APPLICANT:
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 before the. question. Examination papers will be picked up four (4) hours after the examination starts.
% of Category
% of Applicanfs Category Value Total Score Value Category 18 33 1.
Plant Systems 18 33 2.
Procedures -
Normal and Emergency 19 34 3.
Administrative Controls and Technical Specifications 55 100 TOTALS Final Grade All work done on this exam is on my own, I have neither given nor received aid.
Applicants Signature b
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.a 3
SECTION 1: PLANT SYSTEMS
- (1.G.
1.1 What precautions should be observed prior to draining the Scram Discharge Volume after a scram?
(1.@
1.2
~ What systems / requirements would you advise the shift superintendent as being required prior to start-up of a recirculation pump? (Assume plant in Cold Shutdown and plant start-up COL in progress in accordance with GP-2).
(.75) 1.3
' a.
Why are drywell and suppression chamber inerted?
(.75) b.
What are the consequences to the plant if the suppression chamber to drywell vacuum breakers do not properly operate during a LOCA?
(2.0) 1.4 Explain the plant response in the event the on-line EHC pressure regulator falls to high output. (Assume plant operating at 100% Rx power.)
I (1.5) 1.5 Following the automatic initiation of the "A" Standby Liquid Control Pump, the "A" explosive valve falls to open. Explain how this would or would not hamper SLCS operation.
b (2.0) 14 List four modes of the RHR system and briefly discuss the flowpath of each one from discharge of RHR pump to return.
q
' (2.0)
IJ Certain reactor fuels require fuel preconditioning, while others da not.
Is preconditioning necessary o_r unnecessary at the LGS? Explain your choice of answers.
(2.0) 1.8 What signals are required to automatically initiate the following systems: -
a.
LPCI b.
Emergency Diesel Generators c.
ADS d.
- (2.0) 1.9 Assume the following initial conditions:
100% power Feedwater in 3-element control One steam flow transmitter's output signal f alls low.
Assuming no
- {
operator action, how will this falltre effect RFPT operation and what will be the final reactor level?
1.10 With regard to the Redundant Reactivity Control Systems
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(2.0) a.
What will cause on Alternate Rod Insertion?
I (1.0) b.
How will operation of the ARI valves effect speed of control rod
~ insertion on scram?
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_ Enclosure-1
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SECTION 2: PROCEDURES - NORMAL AND EMERGENCY 2.1 List the entry conditions for the following (1.0)
. a.
T-101, Reactor Control (1.0) b.
T-102, Containment Control (1.5) 2.2 A fire occurs in the Control Room which requires evacuation and plant shutdown at the Remote Shutdown Panel. As' a shift advisor,.what immediate operator actions would you advise the Shift Superintendent to check for completion prior to control evacuation as per SE-1 (Plant Shutdown from Outside Control Room)?
(1.3) 2.3 As a shift advisor you are making rounds of the control panels with your-Shift Superintendent (SST) after shift relief. The ACO informs the 55T that he suspects a failed jet pump due to an unexplained decrease in core flow Indication. What other symptorns might you suggest the SST check.
on prior to confirming a failure of a jet pump in accordance with ON-1007 (Three others required).
(2.@
2.4 Briefly discuss the purpose behind use ad GP-18 (Scram Review
-]
Procedure) checkof f list after automatic or manual scram condition.
(2.G 2.5 As per GP-4, Rapid Plant Shutdown, guidance is provided to take the reactor from at power condition to hot shutdown condition. As a shift advisor, what three procedwat steps would you recommend to the SST to check on being completed to ensure an orderly progression to hot shutdown?
(1.0) 2.6 GP-2, Plant Startup, states that with EHC pressure setpoint at 130 psig,
. verify proper operation of the turbine bypass valves and then raise the pressure setpoint to 600 psig. Other than to close the BPV's, why is the setpoint increased and held at 600 psig?
(2.0) 2.7 Given the following conditions, use the attached graphs from T-102, Containment Control, to determine the minimum suppression poollevel required to safely absorb an automatic vessel depressurization:
Reactor pressure = 650 psig Suppression pool temperature = 160 F 0
(2.@
23 As a shift advisor, what symptoms would indicate to you that a 5RY had, in fact,'inadvertantly opened as per 0T-114 (four required).
(2.G 23 As a shift advisor observing a reactor startup from hot shutdown on Unit 1, the SST cautions the ACO to enswe he watches closely for any high notch rod worths which may occur. What conditions might the reactor
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exhibit high rod notch worths and how would it be possible to get into these situations? '
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v-(2.0) 2.10 As a shift advisor, mder what types of plant conditions might you recommend a rapid plant depressurization (via manual ADS Initiation) to the Shift Superintendent?
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SECTION 3: ADMINISTRATIVE CONTROLS AND TECHNICAL SPECIFICATIONS 3.1 Describe the actions that must be taken if the following occur during a reactor startup:
(1.0) a.
RWM falls (1.0) b.
RSCS falls (2.0) 3.2 What topics are required in the verbal report that takes place at shift ttrnover?
3.3 During operation at 100% Rx power, the ACO on Unit 1 informs the SST that the process computer indicates that MAPRAT is equal to 1.01.
Indicate your recommendations to the SST in the following areas:
(1.0) a.
Is a thermallimit being exceeded? Explain.
(1.0) b.
What is the thermal limit consideration associated with MAPRAT.
(3.0) 3.4 The attached portion of Technicial Specifications should be used to answer the following question:
(
Scenario: Plant at 100% Rx power. The D-12 has been out of service due to a faulty blower for three days. Estimated time of repair is five days. About two hours into the shift the P.O. reports to control room that the "C" ESW pump has shutdown during a surveillance test due to motor overcurrent and he has noticed the smell of light electrical smoke in the Spray Pond Pump House.
As the Shift Advisor, what would be your recommendation to the Shift Superintendent in how long plant operation could continue?
(2.0) 3.5 With the plant operations at 100% power, the oncoming shift arrives for relief of the 3:30-11:30 p.m. shift. The relieving shift consists of the following Shift Superintendent (SLO) with accompanying Shift Advisor a.
b.
Shif t Supervisor (SLO)- absent c.
Control Operator (LO) d.
Unit 1 Assistant Control Operator (LO)- absent e.
Plant Operator - absent f.
Assistant Plant Operator b
g.
Inside Auxillary Operator h.
Outside Auxiliary Operator y.
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Enclosuro.1 J. -
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1.
Helpers (2)
The operating shift being relieved has the following compliment with each just completing a double shift because of a major winter storm:
Shift Superintendent (SLO)'
a.
b.
Shift Supervisor (SLO) c.
Control Operator (LO)
- d.
Unit i Assistant Control Operator (LO) e.
Plant Operator f.
Assistant Plant Operator g.
Inside Auxillary Operator h.
Outside Auxillary Operator 1.
Helpr.rs (2)
By use of the attached Technical Specification state what your recommendation to the on-coming Shif t Superintendent would be
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concerning maintaining continued, safe plant operations.
(3.@
34 The following question should be answered utilizing the attached portion of Technical Specifications.
Scenario:
With the reactor operating at 45% power during power ascension tests following a " rod swap" (as per Rx Engineer Instructions) and the completion of control rod scram testing to satisfy Tech. Spec.
surveillance test 4.1.3.2.C., it is determined that the average scram insertion time to notch 39 of all operable control rods is.87 seconds.
The Shift Superintendent, after receiving this information, takes action in accordance with LGS Technical Specifications. As a Shift Advisor, what action should he take? Why?
What is the relationship between a Safety Limit (SL) and a Limiting (1.0) 3.7 a.
Safety System Setting (LSSS)?
(1.0) b.
What are the LGS Safety Limits?
What actions would you expect the Shift Superintendent to take in (1.0) c.
the event a safety limit is exceeded?
(1.G 3.8 Under what plant conditions could you recommend a manual plant shutdown to the Shift Superintendent?
b (1.@
33 As a Shift Advisor Jtst relleving the shift you are making a check of the ACO turnover sheet (attached). What might you recommend to the Shift Superintendent as a result of this review?
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Attachraent 2 JD/rgs ASSISTANT CONTROL OPERATOR SHIFT TURNOVER CHECKLIST Uni t I
Date 2[3! I Shift Y
Off-going ACO dCet d Pe[/A.
[e//c.sa,E SSV b/cy Oncoming ACD
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- 1. Rx MODE
- 2. a.
Restrictions on Reactor Parameters:
U/1 /CCI*
U/2 N/A b.
Remarks: COM3 Wwd b Oc muMe 4.S h m.
3.
Primary Containment Established:
U/1 Yi
/2 AI/A s
- 4. Secondary Containment Established:
U/1 YeS U/2 N/4 5.
SURVEILLANCE LOG OUT-OF-SPECIFICATION READINGS (Explain):
{ i. INSTRUMENTATION BYPASSED OR OUT OF SPECIFICATION-S/U &
RUN MODE ONLY-(Explain):
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Return Deadline Ellff$~
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- 8. Log Book Reviewed: bC (O f f going ACO)
[2.b (Oncoming A00
- 9. Walkaround Completed for control Panels:
N C.
(Offgoing ACO) l NLL (Oncoming ACO)
- 10. Control Panels Required Line-up Verified:
M (Offgoing A00)
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(Onooming ACO)
- 11. Comments or Information to be Passed Ons k
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ENCLOSURE 2
- Senior Licensed Operators at' LGS Unit 'l who participated in a minimum
- 6-week' Hot Participation. Training. (>20% Rx power) program 'at ' Peach Bottom Atomic Power Station:
~
Hgge Position
~ Dates Participated Collins, Greg Shift Supervisor 08/06/84-thru 09/28/84 Crosier,. Thomas V.
Shift' Supervisor 08/28/84 thru,10/09/84 4
Paton, Glenn A.
Shift Supervisor 08/06/84 thrus10/03/84-Romano, Anthony Shift Supervisor 08/28/84 thru 10/09/84 Russell, William N.
Shift Supervisor 09/03/84 thru 10/12/84 Stanley, William Shift Supervisor, 08/06/84 thru 09/20/84 Tindall, Ronald Shift Supervisor 08/06/84~thru 09/19/84 Note:
Charles P. Gillespie -(Shif t Superintendent) ' also attended 6 weeks of training,- 08/06/84 thru 09/24/84, but he is the lone Shift. Superintendent who has a Shift Advisor on his shift.