ML19210A290
| ML19210A290 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/19/1978 |
| From: | Reid B Office of Nuclear Reactor Regulation |
| To: | Herbein J METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19210A291 | List: |
| References | |
| NUDOCS 7910290528 | |
| Download: ML19210A290 (2) | |
Text
.
DISTRIBUUON:
May 19,1978 Docket V NRC PDR L PDR Docket No. 50-289 ORBd4 Reading VStell.o BGrimes JBuchanan RInaran ACRS(16)
Dross GZwetzia~
RDiggs OELD. -
t'etropolitan Edison Company ATTN: Mr. J. G. Herbein 01&E(5)
Gray file Vice President BJones(4)
XTRA 4 P. O. Box 542 BScharf(15)
JMcGouch Reading, Pennsylvania 19603 BHarless Gentlemen:
DEisenhut TAbernathy The Commission has issued the enclosed Amendment No. 40 to Facility Operating License No. DPR-50 for the Three Mile Is'iand Nuclear Station, Unit No. 1.
The amendnent consists of changes to the Technical Socciff-cations in response to your applications dated l'ay 10 and Pay 16,197".
This amendment reduces the allowable measured neutron flux tilt, the allowable axial power imbalance and the allowable position limits for the Axial Power Shaping Rods.
This amendment also adds a license condition, agreed to by you, which requires comparison of measured and predicted power distributions after about 25 effective full power days of operation in this operating cycle.
Copies of the Safety Evaluation and the Notice of Issuance are also enclosed.
Sincerely,
.:s Robert W. Reid, Chief Operating Reactors Branch !4 Division of Operating Reactors
Enclosures:
1.
Amendment No. 40 l407 l73 2.
Safety Evaluation 3.
Notice cc w/ enclosures:
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Metropolitan Edison Company cc w/enclosu-e(s):
G. F. Trowbridge, Esquire Dauphin County Office Emergency Shaw, Pittman, Potts & Trowbridge Preparedness 1800 M Street, N.W.
Court House, Room 7 Washington, D. C.
20036 Front & Market Streets Harrisburg, Pennsylvania 17101 GPU Service Corporation Richard W. Heward, Project Manager Mr. T. Gary Broughton, Safety and Department of Environmental Resources Licensing fianager ATTN: Director, Office of Radiological 260 Cherry Hill Road He al th Parsippany, New Jersey 07054 P. O. Box 2063 Harrisburg, Pennsylvania 17105 Pennsylvania Electric Company Mr. R. W. Conrad Chief, Energy Systems Analyses Vice President, Generation Branch ( AW-459) 1001 Broad Street Of fice of Radiation Programs Johnstown, Pennsylvania 15907 U. S. Environmental Protection Agency Room 645, East Tower Miss Mary V. Southard, Chairman 401 M Street, S.W.
Citizens for a Safe Environment Washington, D. C.
20460 P. O. Box 405 Harrisburg, Pennsylvania 17108 cc w/ enclosure (s) & incoming dtd:
5/10 & 5/16/78 Government Publications Section Governor's Of fice of State Planning State of Library of Pennsylvania and Development Box 1601 (Education Building)
ATTN: Coordinator, Pennsylvania Harrisburg, Pennsylvania 17126 State Clearinghouse P. O. Box 1323 Dr. Edward O. Swartz Harrisburg, Pennsylvania 17120 Board of Supervisors Londonderry Township RFDel - Geyers Church Road Middletown, Pennsylvania 17057 U. S. Environmental Protection Agency Regica III Office
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EIS C00RDIt ATOR Curtis Building (Sixth Floor) 6th and Walnut Streets Philadelphia, Pennsylvania 19106
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UNITED STATES 3"
NUCLEAR REGULATORY COMMISSION i"
WASHINGTON. D. C. 20866
[
METROPOLITAN EDISON COMPANY j
JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 40 License No. DPR-50 1.
The Nuclear Regulatory Conrnission (the Consnission) has found that:
A.
The applications for amendment by Metropolitan Edison Company, Jersey Central Power & Light Company, and Pennsylvania Electric Company (the licensees), dated May 10 and 16,1978, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the ConTnission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application s, the provisions of the Act, and the rules and regulations of the Consnission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Consnission's regulations; D.
The issuance of this amendment will not be inimical to the coninon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CPR Part 51 of the Conrnission's regulations and all applicable requirements have been satisfied.
1487 175 3910290 670 2.
Accordingly, Facility Operating License No. DPR-50 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:
A.
Revise paragraph 2.c.(2) to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
40, are hereby incorporated in the license. Metropolitan Edison Company shall operate the facility in 2.:a.nf ance with the Technical Specifications.
B.
Add paragraph 2.c.(3) to read as follows:
(3) Power Peaking Metropolitan Edison Compai.y shall measure the radial and total power distribution present in f he core at equilibrium xenon at or above 75% power after 25 (+20%) EFPD of exposure in Cycle 4.
Metropolitan Edison Company shall compare these distributions with power distributions calculated for this power level and exposure in Cycle 4, and submit the results to the NRC within 15 days of comple-tion of the measurements.
If the d.iference between the measured and observed power peaks exceeds 11% for radial peaking or 13.5% for total peaking, Metropolitan Edison Company shall reduce the full power rating of the facility by one percent for each percent that the peaking exceeds these respective limits, and notify the NRC pursuant to Technical Specification 6.9.2. A.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULAT COMMISSION m//
fey Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications
}4b7 l7b Date of Issuance: May 19,1978
ATTACHMENT TO LICENSE AMENDMENT NO. 40 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Revise the Appendix A Technical Specifications as follows:
Remove Paces Insert Paces Figure 2.3-2 Figure 2.3-2 3-34 & 3-34a 3-34 & 3-34a s
3-36 3-36 Figure 3.5-2E Figure 3.5-2E Figure 3.5-2H Figure 3.5-2H The changed areas on the revised pages are showr. by marginal lines.
1487 177 l
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SETrolNTS FOR Rf ACTOR POT!R lWAL ANCE 151 1. CTCit 4 (TRCH 0 TO 12515 ETFD)
F19ure f 3 2 1487 178
+ Amendment No. pf, g, g, 40
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If a control rod in the regulating or axial power shaping groups is declared Snoperable per Specification k.7.1.F.,
opteration rmy continue prcvided the mde in the group are positioned such that the rod that vos declared inoperable is amintained within allowable group average position limits of Speci rleation b.7.1.2.
3 If the inoperable rod in Paragraph "e" above is in groups 5. 6, 7, or 8, the other rods in the group any be trimmed to the same Position.
Tiermal operation of 100 percent of the thermal power allovable for the resetor coolant pump combination may then continue provided that the rod that was declared inoperable is maintained within allovable group average position Ifnits in 3525 3 5.2 3 Tb, worth of single inserted control rods during eritieslity are limited by the restrictions of Speelfication 31 3 5 and the control Rod Position Lit:1ts defined in Specification 3.5.2 5.
3 5 2.h Quadrant tilt:
Except for physics tests the quadrant tilt shall not exceed a.
+3.Si as determined using the full incore detector system.
{
b.
When the full incore detector system is not available and except for physics tests quadrant tilt shall not exceed +190%
l as detemined using the minimu:n incore detector system.
When neither incore detector syste:s above is svallable and c.
except for physics tests quadrant tilt shall not exceed +1.96%
l as detert:ined using the po er range r.hannels dispinyed on the console for each quadrant (out of core detector system).
d.
Except for physics tests if quadrant tilt exceeds tha tilt limit pover shall be reduced liasediately to below the power level cutoff (see Figures 3 5-2A, and 3.5-2B.
Moreover, the Power level cutoff value shall be reduced 2 percent for each 1 percent tilt in excess of the tilt linit.
F'or Jeep than four ptmp operation, thermal power shall be reduced 2 percent of the thermal pover allovabic for the reactor coolant pumn combination for each I percent tilt in excess of the tilt linit.
e.
Within a period of b hours, the quadrant power tilt shall be reduced to less than the tilt Ilmit except for physics tents, or the following adjustnents in setpoints and limits shall be made:
1.
The protection systen reactos pover/ imbalance envelope trip setpeints shall be reduerd 2 percent in power for each I percent tiJt.
1487 179 w
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,Amenament No. )/, % [ 40
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The centrol rod grour withdrosal Itat ts (rigures 3 5-2A, 3 5-PB, 3 5-2C, 3.5-?D, and 3 5-2M, shall be reduced P percent in pcwer for eac5 2 percent tilt in excess of the tilt limit.
3.
'the operational imbalance limits (rigure 3.5-7r, and 3 5-2F) shall be reduced 2 percent in power for each 2 percent tilt in excess of the tilt limit.
f.
F.xcept for physics or diagncstic testing, if quadrant tilt is in excess of +26.75% determined using the full ineere detector system (TIT), or +15.211 determined using the nintaws incore detector system (MIT) if the TIT is not available, or +2?.9?T determined using the out or core detector system (OCT) vben neither the FIT nor HIT are available, the rea: tor vill be placed in the hot shutdovn conda tion. Diariosite testinc during power operatien vith a quadrant tilt is perint t ted provided that the therral power allovsble is restricted s,s stated in 3 5 2.b.d above.
g.
Quadrant tilt shall be monitored on a minimum frequency or onen every two hours during power operation above 15 percent of rated pover.
1487 180 3-r..
Amendment No.M,,3fr; X 40
+
The ?5e5 percent overInp M t v. en succernive centrei rod groups is allowed since the vorth of a rod is lower at the upper and lover part of the stroke.
Centrol rods este arranged in groups e r banks defined as follows:
Group Fuaetion 1
safety D 0
n 2
Bntety'
@ D W
'b 3
Safety I
J b b
Safety 3
Regulating 6
segulating 7
seguisting (Xenon transient override) 8 APSR (axial power shaping bank)
Control rod groups are withd avn in sequen;e beginning with group 1.
Groupa
- 5. 6 and 7 are overlapped 25 percent. The normal position at power is for group 7 to be partially inserted.
The rod position limits a.re based on the mest liciting of the following three criteria: ECCS power peaking, shutdown margin, and pctentia2 ejected rod worth. As discussed above, compliance with the ECC5 pcVer peaMng criterion is ensured by the rod position limits.
The mini =u= available rod North, consistent with the rod position limits, provides for schieving hot shutdown by rwacter trip at any ti=e, assuming the highest worth control rod that is withdravn remains in the full out position-(1). The rod position limits also ensure that inserted rod groups vill not contain single rod vorths greater thas: 0.65% Ak/k at rated pover.
These values have been shown to be safe by the safety analysis (2) of the hypothetical ro.2 ajeetion accident. A maximum single inserted control rod vorth of 1.0% ak/k is allowed by the rod position limits at het zero power.
A single inserted control rod worth 1.05ak/k at beginning cf life, hot, sero power would result in a lover transient peak thermal power and, therefore, less severe enviren= ente.1 consequences thrm -
0.65% Ak/k ejected rod vorth at rated pover.
The plant computer vill sean for tilt and imbalance and vill satisfy the technical specification requirements.
If the computer is out of service, than manual calculation for tilt above 15 percent power sad imbalance above 40 Percent pover must be performed at least every two hours until the costputer is returned to service.
The quadrant power tilt limits set forth in Specification 3.5 2.h have been established within the thermal analysis design base using an actual core tilt of tk.92% which is equivalent to a +3.6L% tilt mengured with the full incore instru=entation with measurement uncertainties included.
During the physics testing program, the high flux trip setpoints are admini-stratively set es follows to assure an additionni safety mar 6 n is provided:
1 Test Power Trip Setpoint 0
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5cr 1487 181 60 Scl; 50 60t 75 8%,
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1487 182 Amendment No. y', pf, /I, 40
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Amendment No. g g 40