ML19224A112
| ML19224A112 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/25/1978 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7809110124 | |
| Download: ML19224A112 (5) | |
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'o UNITE D $T ATES ft NUCLE AR REGULATORY COMMisslON s hf!.,k WASHING 10N D. C. 20555 g
August 25, 1978 Docket No. 50-320 Metropolitan Edison Company ATTN: Mr. J. G. Herbein Vice President P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
SUBJECT:
FACILITY OPERATING LICENSE NO. OPR-73, AMENDMENT NO. 6 On August 17, 1978, we issued Amendment No. 6 to Facility Operating License No. DPR-73. Pages 2-6, B 2-6, and 3/4 7-3a of the amended Technical Specifications contained typographical and editcrial errors as noted on the attached pages.
The correct wording is shown marked-up by band. These corrections will be included in a future amendment.
Si cgrely.
CD
' % d,'
Steven A. Varga, Chief,
Light Water Reactors Bra 4
Division of Project Panagement ccs:
Listed on following page
Enclosures:
Marked-up pages 78 0 9 ll O lli 4 - gen GPus@
i - c ~J t av%
Metropolit1n Edison Company ccs:
George F. Trowbridge, Esq.
Alan S. Rosenthal, Esq. Chairman Shaw, Pittman, Potts & Trowbridge Atomic Safety and Licensing 1800 M Street, N. W.
U. S. Nuclear Regulatory Cuanission Washington, D. C.
20036 Washington, D. C.
20b55 Mr.1. R. F inf rock Jersey Central Power and Light Compay Dr. W. Reed Johnson, Merber Madison Avenue at Punch Bowl Road Ato:nic Safety and Licensing Morristown, New Jersey 07960 Appeal Board U.S. Nuclear ReguTutory Commission Mr. R. Conrad Washington, D. C.
20555 Pennsylvania Electric Conpany 1007 Broad Street Jerome E. Sbarfman, Esquire, Member Johnstown, Pennsylvania 15907 Atomic Safety and Licensing Appeal Board Chauncey R. Kepford, Esq.
U.S. Nuclear Regulatory Co;nmission Chairman Washington, D. C.
20555 York Comnittee for a Safe Environment 433 Orlando Drive State College, Pennsylvania 16801 Mr. Richard W. Heward Project Manager GP'J Service Corporation 260 Cherry Hill Road Parsippany, New Jersey 07054 Mr. T. Gary Broughton Safety and Licensing Manager GPU Service Corporation 260 Cherry Hill Road Parsippany, New Jersey 07054 Edward Luton, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. Gustave A. Linenberger Atomic Safety and Licensing Board U. S. Nuclear Regulatory Connission Washington, D. C.
20555 Dr. Ernest O. Salo Professor, Fisheries Research Institute, WH-10 College of Fisheries University of Washington Seattle, Washington 93195 1_[(3Pf" p919P a c.. -
. $0kh g
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- TABLE 2.2-1 (Continued).
Yg REACTOR PROTECTION SYSTEM INSTRUMENTATION TRIP SETPOINTS m
3 FUNCTION UNIT TRIP SETPOINT ALLOWABLE VALUES r-
[
8.
Nudlear Overpower 1 125% of RATED TIIERMAL POWER
< 125% of RATED TifERMAL POWER p
based on Pump Monitors (y) with three pumps operating with three pumps operatingi E"6
< 56.9% of RATED TilERMAL POWER
< 57.18% of RATED TifERMAL POWER sith one pe p operating in each loop Gith one pump operating in each loopil C
D 5
< 0% of RATED f!![ PHAL F0VER with
< 0.28% of RATED THERMAL POWER with t
H
[
two pump operating in one loop and Two pumps operating h one loop and p
no pump operating in the other loop no pump operating in the other loopf g C
d 1 0% of RATED TilERMAL POWER with
< 0.28% of RATED TIIERMAL POWER with p _-
no pumps operating or only one pump no pumps operating or only one pump operating operatingi i
9.
Reactor Containment Vessel 1 4 psig 4 psigh I
a 1
O g '"a (3) Trip ci be manually bypassed when RCS pressure i II20psigbyactuatingShutdownbypassprovidedthat:
a r y b
a.
The Nuclear Overpower Trip Setpoint is < 5% of RATED TilERMAL POWER h
b.
The Shutdown Bypass RCS Pressure - High Trip Setp
'.t of 1 1(20psigisimposed,and c.
The Shutdown Bypass is removed when RCS Pressure if00 psig.8 9
R
- Allowable value for Channel functional Test.
g
- Allowable value for Channel Calibration.
R
- Allowable value for Channel functional Test and Channel Calibration.
E a
.E a
LIMITING SAFr.TY SYSTEM SETTINGS BASES The AXIAL POWER IMBALANCE boundaries are established in order to prevent reactor thermal limits from being exceeded. These thermal limits are either power peaking kw/ft limits or DNBR limits. The AXIAL POWER IMBALANCE reduces the power level trip produced by the flux-to-flow ratio such that the boundaries of Figure 2.2-1 are produced. The flux-to-flow ratio reduces the power level trip and associated reactor power-reactor power-imbalance boundaries by 1.05% for a li flow reduction.
RCS Pressure - Low, Hich and Variable low The High and Low trips are provided to limit the pressure range in which reactor operation is permitted.
During a slow reactivity insertion startup accident from low power or a slow reactivity insertion from high power, the RCS Pressure-High setpoint is reached before the Nuclear Overpower Trio Setpoint. The trip setpoint for RCS Pressure-High, 2355 psig, has beer established to maintain the system pressure below the safety limit, 2750 psig, for any design transient. The RCS Pressure-High trip is backed up by the pressurizer code safety valves for RCS over pressure trotection, and is therefore set lower than the set pressure for these valtes, 2500 psig. The RCS Pressure-l Hign trip also backs up the Nuclear Overpower trip.
9.
The RCS Pressure-Low, 1/00 psig, and RCS Pressure-Variable Low, (13.00 T I
tain the d. F-5SS7) psig, Trip Setpoints have been establisht) to main-U MB ratio greater than or equal to 1.30 for those design accidents that result in a pressure reduction. It also prevents reactor operation at pressures below the valid range of DNB correlation limits, protecting against DNS.
Due to the calibration and instrumentation errors, the safety analysis used a RCS Pressure-Variable Low Trip Setpoint of (13.00 T F-5927) psig. l out Nuclear Overpower Based on Pump Monitors In conjunction with the power / imbalance / flow trips the Nuclear Over-power Based On Pump Monitors trip prevents the minimum core DNBR frem decreasing below 1.30 by tripping the reactor due to the loss of reactor coolant pump (s). The pump monitors also restrict the power level for the number of pumps in operation.
THREE MILE ISLAND - UNIT 2 B 2-6 Amendment No. 6 4
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MF CO27
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g TABLE 3.7-4_([ontinued),
mN STEAM LINE SAFETY VALVES PER STEAM GENERATOR H
A VALVE NUMBER LIFT SETTING _(1 1%)*
ORIFICE SIZE
,. 4 p
)
D
[ square inches)
E5 h.
MS-R220 1050 psig 16 e
c c.
MS-R260 1050 psig 16 d.
MS-R2 8 1050 psig 16 sh)
e.
MS-R23B TJ 1065 psig 16 9
['
f.
MS-R28B 1065 psig 16 g.
MS-R248 1075 psig 16 h.
MS-R290 1075 pr'.
16 1.
MS-RP50 1102 psig 16'.
J.
MS-R308 1102 psig 16 9
b
- t n
o 5
'The lif t setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
,