ML19338C752
| ML19338C752 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/27/1980 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578, TASK-2.E.1.2, TASK-TM NUDOCS 8009040301 | |
| Download: ML19338C752 (13) | |
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7 BALTIMORE GAS AND ELECTRIC COMPANY P. O. B O X 1475 O A LTIM OR E, M ARYL AN D 21203 August 27, 1980 ARTHUR E. LUNOVALL, d54 v.cc % rs.cr. c svPP67 Of fice of Nuclear Reactor Regulation U. S. Nuclear Reculatory Cc: :ission Washington, D. C.
20555 Attn:
Mr. P. A. Clark, Chief Cperating Reactors Branch No. 3 Division of Licensing
Subject:
Calvert Cliffs ?;uclear Power Plant Units Nos. 1 & 2, Dockets Nos. 50-317 & 50-318 Short Tern Lessons Learned NUR m 0578, Item 2.1.7a.
Reference:
BG'<E letter dated 1/25/80 from A. E. Lundvall, Jr.
tn R. W. Reid, Automatic Initiation of Auxiliary Feedvater System.
Gentlemen:
LUREG 0578, Item 2.1.7a, requires implenentation of a safety-grade auto -start of auxiliary feedvater ( AFW) by January 1,1981. An NPC review of design prior to implementation is required. This letter and enclosures describe the proposed nodification.
It should be noted that additional changes to the auxilia y feedvater system to meet the requirements of the Bulletins & Orders (B&O) Task Force are being engineered, including nodification of AFW pump turbine-drive steam supply valves to air operated AC-independent valves and the addition of a notor driven MW rimp and asrociated piping.
'~hese ad<litional changes are nazt of a separate effort to upgrade the AFW system in light of the E!.0 letter of 11/7/79 The schedule for these changes vill be described in a separate submittal.
Current information suggests the possibility of corpletion of these auditional changes in 1933.
The existing auxiliary feedvater system is shown on enclosure No. 1.
Note that steam to the at..111ary feed pump turbines fron stean generator No. 11 passes through MOV h070. Steam to the turbines from steam Fenerator No.12 passes through MOV h071.
'~he turbines can be suppliet' stenn from either or both steam generators.
'~he schematic for control of MOV 5070 is shown on enclosure No. 2.
The schematic for ?OV h071 is similar. The
.eource of power for control and operation of "0V h070 is MCC 11hR. MCC 11hR is in turn powered from h kV Unit Bus 11.
Fnerrancy power to h kV Unit Bun 11 is provided by Emergency Diesel Generator 11.
The sources of power for control and operation of MOV h071 is MCC 10hR. MCC 10hR is in turn povered fron h kV Unit Bus lb.
Emercency power to h kV Unit Bus lh is available from Fnerrency Diesel Generator IP, Geparation of cabline is maintained by the desien.
Enclosure No. 6 lists power sources for AFW system control devices.
I POOR QUAUTY PAGES 9
- 7'5 Mr. P. A. Clark Pace 2 Aur,ust 27, 1980 Fnclosure No. 3 is the 3cric drawing for the AFW pump turbine-drive stean supoly valves. Autcratic start of the AFW nump turbine-drives occurt on identification of low level in either steam generator. When low level in a steam renerator is sensed on two of four independent IEFAS sensor channels,
both turbine-drive stean supply valves are commanded to open following a time del ay. The cotnand to open is scaled in until the valve is fully open.
Reference above specifies that a 1-minute tine delay is necessary and suf-ficient to prevent a reactor restart due to auto initiation of AFW followinc a Steam Line Preak accident.
Fnclosure No. h shows the lorie used to renerate the time delay start signals.
Enclosure No. 5 shove the Actuation System Schenatic.
Note the use of two tire delay relays per actuation channel to nrovide single-failure proof protection ngainst a possibly unsafe early initiation of AFW.
The above discussion presurroses that the stean supply valve control room handsvitches are in the auto cosition.
"'ne " pull-to-lock" pcsition en the handsvitch overrides a cor and to open and shuts the steam cunrly valve.
Annunciation of the handsvitch in tha " pull-to-lock" position is trovided.
Tnis handsvitch p3sition is necessary to allov keeping the stean supply valves closed during plant heat-up.
She operator may at any time open the steam supply valves using the control room handsvitches.
Actuatien of AFW on low stean rener1 tor level na ocposed to sene other initiating parameter (s) vac selected tecause level is the tost direct indicator of the quality of the steam renerator as a heat sink for the RCS.
Start-up of AFW, based en level, ensures that suf ficient water inventory is naintained at all times for effective renoval of heat from the primarv systen.
There is no need to actuate AFW on less of offsite powcr or loss of main feed since both of these conditions will troduce a low level start of /}W.
A setpoint equivalent to the steam renerator level reactor trip setpoint vill be used.
The inventory in the staam generators following a trip at low level is sufficient to renove the decay heat renerated in the first 10 minutes after the trip. The auto initiation of AFV vithin 3-5 minutes after trip at low level ensures sufficient inventory is available for decay heat renoval prior to establishtent cf AFW flow.
Cavitation at the suction of the AFW namps can occur due to loss of NPCH caused by excess suction line velocities.
Cavitation can occur at any AFV regulating valve settinc dependine on steam generator pressure.
With the valve vide open, cavitation can occur within ninutes of AFW actua-tion due to the loverine of renerator pressure by the operation of the steam dumps. The preccure at which cavitation occurs is decreased as the valve disc is moved toward its seat, but flow at hich steam generator pressures is reduced. Measures to protect the purps vill include administrative control of the AFW rerulating valve position as set by the hand-indicating controllers in the control room and nrovidine back-up air to the fail oren valves from the salt-water air conpressors.
The back-up cource of control air is necessary since the instrument air compressors are shed from the safety buses on loss of offsite power and not sequenced back on if a demand for safety injection is nresent.
The adninistratively controlled
,e.q Mr. R. A. Clark Page 3 August PT, 1980 linit on AW regulating valve position has been selected to protect the AW pumps down to a steam generator pressure of '500 pain.
At this setting, the flov to the steam generators when pressure is at the full flow relief valve setncint of 1100 psia is '300 gpm.
Since the decay hent ; enerated within the first 10 minutes after a trip can be covered by steam cenerator inventory, any AW flow during this period of time adds to the nreviously established safety *r.argin guaranteeing the adeqancy of the steam generator as a heat sink for the reactor ecolant system. She operator may increase flow after AW syste:r initiation at anf ti.e to establish the lesir<d ECS cooldovn rate.
Tentine of input bistables and 2/h coincidence ler.ic entrixei vill be in ace.wdance with established test procedures currently applied to EGFAS.
A Tech Spee change letter vill be submitted at a later date.
"'he tining of testing and test requirements vill te addressed in this letter.
2 % F intends to tegin installation durinc the upconing refueline outares with or without NBC approval.
If ?;EC anproval b.as not been received by the end of the outage, then hand-Indicating-centrollers in the contral roem vill be net to aintain AW re;ulating valves in the fully clcsel cosition.
This vill prevent AW flow to the steam reneratorc but vill n!!ov suto-cta.rt of the AW purrs on recire.
Very truly yours, cc:
J.
A. Biddison, Fsquire G.
P. Trowbridge, Esquire l'r. E. :.. Cor.ner, Jr. - N?C 1
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rneiosure !!c. G POWER SUPPLY DATA TABLE 2
1,
t! NIT DEVICES PO'4ER SUPPLY FACILITY ASSOC. S/G i
1
'40V 4070 t:CC 114R WA Stn fron 11 to 3GFPT hdr i
1
'tO'! 4071 74CC 104R.
73 Stn from 1.? to 90FPT h:!r i
1 HIC 4511 if01 PA Aux FeeI to 11 1
itic 451.'
LYO?
RB Attx Feed to l
l 1
- IC 3 E 0 lYO' WD t
I 1
Auro init.
lYO1 RA Low level in either
'T Ro tay:s-Chan A i
1 Au;o nit.
1YO' A3
'. c./ level in either E Relava-Chan U
?
!!IC 4511 2YOl MA Aux Feed to 71
?
HIC 451?
? YO')
RD Aux Feet to
'2 2
MIC 3987 2YO!
MA
- A 2
ilIC 3339 2YO2 MS
- A i
?
- 137 40'.'O
- CC ? i d:t MA Stn fron ?1 to qr,FPT
}
bde 4
1 I
2
'10V 4071
'<CC 204R E3 Str frcm ?? to sqFPT l
h ir 1
-2 Auto IniL.
2YOi RA Low Trvol in e; ther SG 1
Helayn-Chan A i
?
Auto Init.
?YC?
E'l Low level in either SG
'Relaya-Chan H I!o te -
Aux F'.! ite.",. CV'c P.O. on loan of air f. power
'YO1 in vital ac from inverter flo. Il ccnnected to lh t t. Bus 11 r
j lYO? ic vital ac Crun inverter tio. 12 connecteti to Batt. Hun ?1 c'Y01 in vital ac fran inverter No. ?! connecteri to Patt. Ibin ' 11 3YO? in vital ac from inverter rio. ?' connected to flatt. Bun 21 I
l I-
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