ML19319D137
| ML19319D137 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/14/1978 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003130707 | |
| Download: ML19319D137 (5) | |
Text
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REGULATORY INFORi!ATION DISTRIBUTION SYSTEM (RIDS)_
DISTRIEUTION FOR INCOMING MATERIAL
' 50-302/
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PEC REID R W ORO: STEWART U P DOCDATE: 06/14/78 NRC FL PWR DATE RCVD: 06.19/7@
COT TYPE: LETTER NOTARIZED: YES COPIES RECEIVED 9UNEC T -
LTR 1 ENCL 1 FORWARDING REPT JUSTIFYING STARTUP AND INTERIM OPERATION OF-UNIT 3 AT FULL PLF. FRIOR TO IMPLEMENTATION OF A PERMANENT SOLUTION TO TQE ECCS SMALL PREAKS
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('NALYSIS PROBLEM OF SUBJECT FACILITY.
NOTARIZED 06/14/78.
PLANT NAME. CRYSTAL RIVER lt3 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL: g
- r w e er-c.* * * ** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ****"************
GENERAL. DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIEUTION CODE A001)
FOR ACTION:
BR C M 4 9ft4 BC**W/7 ENCL INTERNAL:
prn c " '-.W/ ENCL NRC PDR**W/ ENCL 1 L EMW/7 ENCL-DELD**LTR ONLY HANAUER**W/ ENCL CORE PERFOR"1ANCE ER**W/ ENCL An FOR OPER TECH *rW/ ENCL ENGINEEPING BR**W/ ENCL REACTOR GAFETY BR HW/ ENCL PLANT 3YSTEMS ER**W/ ENCL EEBM tJ GNCL EFFLUENT TREAT SYS+*W/ ENCL J.
?!CGOUGH**W/ ENCL EXTERNAL:
LPDR'S CRYSTAL RIVER, FLMU/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL L
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Florida gf W. P. STEWART. OIR ECTOR POWER PRoDUCTloN coaeoaano=
June 14, 1978 File: 3-0-3-a-3 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Mr. R. W. Reid, Chief Operating Reactors Branch #4
Subject:
Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 ECCS Small Breaks Analysis
Dear Sir:
Attached for your review is a report that justifies startup and interim operation of Crystal River Unit 3 at full power prior to implementation of a permanent solution to the ECCS Small Breaks Analysis problem.
This report is in accordance with my letter of May 5,1978.
The report, describing the permanent solution to this problem, will be filed on or before July 21, 1978.
Please advise if further discussion is desired.
Sincerely, FLORIDA POWER CORPORATION I
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W. P. Stewart WPS/RB/hw 4/7
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General Office 3201 Tnirty-fourtn street soutn. P.O. Box 14o42. St. Petersburg. F!onda 33733 813-866-5151 I
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. STATE OF FLORIDA' COUNTY OF PINELLAS.
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W.P. Stewart states that he~is..the Director,IPower Production,'of -
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/ F1orida ' Power: Corporation; that he'is_.' authorized' on the 'part.of -
= said company.to sign and. file with the Nucle ~ar. Regulatory Commission-the information ~att' ached thereto;1and that all such statements made and matters set'-forth therein'are' true an'd correi:t to the.best of his
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knowledge, 'information and bel.ief.
k W.P.' Stewart Subscribed and sworn to before me, a Notary Public in and for the State and. County above named, this 14th day of' June, 1978.
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Notary Public '
. Notary Public,' State of_-Florida at Large,.
'. My ' Commission. Expi res:
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r, On May :1,Il'978, Babcock'.& Wilcox filed the report, " Analysis of Small Breaks in the Reactor Coolant Pump Discharge Piping for the B&W < Lowered Loop FA Plants," with the Commission (Mr. J.H. Taylor to Mr. R.L. Baer).
In that ~ report, certain operator action was described as being required for a typical plant operating at_2568 MW to mitigate the " worst case" small break in the reactor coolant pump discharge piping.
Rated Thermal Power for. Crystal River Unit 3 is _2452 MW thus the referenced operator :
. action would also mitigate.such an accident at CR 3.
This. report' describes how the required operator action has been instituted at Crystal River and therefore startup and subsequent operation until the installation of a permanent solution is justified.
The required operator action is in four steps; each of these steps'will be-addressed separately.
A schematic of the ECCS is in FSAR' Figure 6-2 and the Makeup and Purification System is shown in FSAR Figure 9-2.
Emergency Procedure - Loss of RC/RC Pressure (EP-106 rev. 13) has a section entitled " Failure of HPI Pump to Start During ES Actuation."
The steps referenced below are from _this ;section.
1.
"Upon ESFAS signal check for flow through both HPI trains" Step 4.1.1 has the operator check the ES panel to determine if.
there is flow thru both HPI trains.
2.
"If no flow in one train: - open pump header cross-connect valves" Step 4.3.3 requires the operator to open MUV-4.
n u h one of the two cross-connect valves between MVP-B and MUP-C.
The other velve (MU7-3) is open per a revision to the Makeup and Purification System operating procedure (0P-402, rev.14) in Valve Check List I.
"- check HP1 valve position and open if closed" Step 4.3.1 performs this action.
In addition to the additional flow as a esult of these two steps, Step 4.3.2 attempts to start the failed HPI oump for normal two pump HPI flow.
3.
" Secure flow through-normal makeup line if flow is indicated" Actuation of either A or B Engineered Safeguards System automatically isolates the normal letdown line and the reactor coolant pump seal return line by closing the following valves:
ES "A" ES "B" Normal Letdown Line MUV-40 & 41 MUV-49 RCP Seal Return Line MUV-258, 259, MVV-253 260 & 261 l
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4.
" Throttle HPI valves as ' required to. balance flow and meet run out'
. limits"-
-Step 4.3.4 requires the operator to balance the HPI flow to achieve
.no more.than 150 gpm thru any one of the four HPI lines.
The 150 gpm is 30%-of the 500 gpm'HPI flow for one HPI pump.
Makeup pump run out-is prevented _ by stop-check valves MUV-2, 6, and 10 for_MUP-C,EB'& A, respectively.
These valves are preset to prevent a pump run out condition.
The operating personnel will review this revision to EP-106 via the normal revision process. Administrative Instructions - Conduct of Operations (AI-500), Step ~2.10 " Plant Operating Quality Assurance.
Manual (P0QAM), Revision Notification" states "... When the revisions are approved, they will be transmitted along with a Form 912235, Char.ge
-Notification, to the Shift-Supervisor who will initial the Change Notification, signifying that each ' member of his shift has been informed of the revision.
It is the responsibilit, of each Shift Supervisor to insure that his shift is informed.
Forms which have been signed by all Shift Supervisors shall be returned via the Operating Engineer to the Operations Superintendent who will file the change form for the latest revision in the P0QAM Revision Log."'
In addition, all operators participating in the week-long B&W simulator review (to end July 28) will have an exercise that includes this " worst' case" small break and will perform the operator action required to mitigate the accident.
The review of the emergency procedure, the simulator training, and normal operator knowledge of the location and operation of the makeup pump cross-connect valves is sufficient to ensure that the " worst case" small break in the reactor coolant pump ' discharge piping accident will be mitigated at Crystal River Unit 3.
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