ML19210B084
| ML19210B084 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/05/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7911040031 | |
| Download: ML19210B084 (4) | |
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Docket File '-
Gray File January 5, 1978 NRC PDR 4 Extra Cys L PDR VStello ORB #4 Rdg XRGoller BScharf (10)
BHarless Occket No.:
50-239 TJCarter JMcGough OPA, Clare Miles RReid 3RX Dross GZwetzig RIngram I'etropolitan Edison Compeny Attorney, OELD ATTN:
Mr. J. G. Herbein 0ISE (5):
Vice President DEisenhut
- p. O. Box 542 BJones (4) p.eading, Pennsylvania
- 19C03,
...TBAbernathy JRBuchanan Gentleren:
ACRS (16)
Ey letter dated Havenber 13, 1977, you requested atendrent of Facility Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit No. 1 (TMI-1). The re<"scsted anendment would change the code safety valve capacity stated in the basis.for Technical Specification 3.1.1. 3.
In the attachment to the above letter.you state that the need for the change arises from the discovery that relief rate of the code safety valves as stated on the valve.. nameplate is less than.the relief rate used in the original calculatfoo of imximum reactor coolant systen pressure following a postulated feedwater line break.
The attachment to your letter also supplies the results of new calculations perferred using the corrected relief rate and a trip. string pressure delay tito characteristic of the pressure sensors currently installed at T!!I-1.
These calculations indicate that the effect of these chances is to increase the peak reactor coolant system pressure from 2734.2 psig to 2734.5 psic.
Because the corrected peak pressure rerains below the safety limit of 2750 psig, as, stated in. Specification 2.2.1,.and Lecause the increase in peak pressure is only 0.3 psi, we conclude that there is no significant adverse effect on the health and safety of the public and no significant reducticn in safety.rargin.
Accordingly, un further conclude that there is ro need to.nodify the facility limiting safety systen settings as a result of discovery of this error.
a Y
J '
10 rerali: n Edison Crpa:P/ scause the h313 portion cf facility technical specific 3ticns rerely
?r0'/ ides an nclanation of the technical basis for licence requiremnts, revisior of the basis Ecction dccs not require anendrcnt of the license unless t: fro are corresponding chances in operating requirer.'ents.
Bacause n a present change in this t: asis does not require a chance in operating requirements, we are not amcnding the TII-l license, but rather are issuing the attached corrected pace 0-2.
Sincerely.
-.y..
Rchert II. Reid, Chief Operating Reactors Eranch f4 Division of Goerating ?.eactors Attacinnt:
Corrected Page 3-2 cc w/.ttachnent: See next page 1587 546 m <e -3/
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Metropolitan Edison Company cc w/ enclosure (s):
G. F. Trowbridge, Esq.
Mr. Harry B. Reese, Jr., Chairman Shaw, Pittman, Potts, & Trowbridge Board of County Commissioners 1800 M Street, N.W.
of Dauphin County Washington, D.C.
20036 Dauphin County Court House P. O. Box 1295 GPU Service Corporation Harrisburg, Pennsylvania 17120 Richard W. Heward, Project Manager Mr. T. Gary Broughton, Safety and Department of Environmental Resource Licensing Manager ATTN:
Director, Office of 260 Cherry Hill Road Radiological Health Parisppany, New Jersey 07054 P. O. Box 2063 Harrisburg, Pennsylvania 17105 Pennsylvania Electric Company Mr. R. W. Conrad Chief, Energy Systems Vice President, Generation Analyses Branch (AW 459) 1001 Broad Street Office of Radiation Rroc ams Johnstown, Pennsylvania 15907 U. S. Environmental Protection Agen:
Room 645, East Tower Mr. Weldon B. Arehart, Chairman 401 M Street, S.W.
Board of Supervisors of Londonderry Washington, D.C.
20460 Township RFD #1, Geyers Church Road U. S. Environmental Prote:tign Ager.c Middletown, Pennsylvania 17057' Regior) III Off'i'ce
- ATTN:
EIS COORDINATOR Miss Mary V. Southard, Chairman Curtis Building (Sixth Floor)
Citizens for a Safe Environment 6th and Walnut Euilding P. O. Box 405 Philadelphia, Pennsylvania 19105 Harrisburg, Pennsylvania 17108 cc w/ enclosure (s) & incoming dtd.:
Government Publications Section 11/18/77 State Library of Pennsylvania Governor's Office of State Planning Box 1601 (Education Building) and Development Harrisburg, Pennsylvania 17125 ATTN:
Coordinator, Pennsylvania State Clearinghouse Dr. Edward O. Swartz P. O. Box 1323 Board of Supervisors Harrisburg, Pennsylvania 17120 Londonderry Township R.F.D. #1 - Geyers Church Road Middletown, Pennsylvania 17057 1537 347
Bases The limitation en power operation with one idle RC pu=p in each loop has been i= posed since the ECOS cooling performance has not been calculated in accordance with the Final Acceptance Criteria requirements specifically for this node of reactor operation. A time period of 2h hours is allowed for operation with one idle RC pu=p in each 1 cop to effect repairs of the idle pump (s) and to return the reactor to an acceptable ce=bination of operating RC pumps.
The 2h hours for this =cde of operation is acceptable since this =cde is expected to have censiderable =argin for the peak cladding temperature limit and since the likelihood of a LOCA vithin the 2h hour period is considered very remote.
A reactor coolant pu=p or decay heat removal pump is required to be in operation before the boren concentratica is reduced by dilution with
=akeup water.
Either pump vill provide =ixing which vill prevent sudden pcsitive reactivity changes caused by dilute coolant reaching the reactor.
One decay heat re= oval pu=p vill circulate the equivalent of the reactor coolant system volu=e in ene half hour or less.
The decay heat re= oval system suction piping is designed for 300 ? and.
370 psig; thus, the system can rencve decay heat when the reacter coolant system is below this temperature.
(2, 3)
One pressurizer code safety valve is capable of preventing overpressurization when the reactor is not critical since its relieving capacity is greater than that required by the sum of the available heat sources which are pump energy, pressurizer heaters, and reactor decay heat.
(h) Both pressurizer code safety valves are required to be in service prior to criticality to conform to the systes design relief capabillties.
The code safety valves prevent overpressure for a rod withdrawal or feedvater line break accidents.
(5) The pressurizer code safety valve lift set point shall be set at 2500 psig 21% allowance for error and each valve shall be capable of relieving 280,800 lb/h of saturated steam at a l
pressure not greater than three percent abcve the set pressure.
References (1) FSAR, Tables 9-10 and k-3 through h-7 (2) FSAR, Sections h.2.5.1 and 9 7.2 3 (3) FSAR, Section h.2 5.h (k) FSAR, Sections h.3.10.h and h.2.h (5) FSAR, Section h.3.7 I
i537 348 Amendment No.,1?T'28 3-2