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UNITED STATES
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l WASHINGTON. D.C. 20543 September 28, 1973 Docket No. 50-219 Jersey Central Power & Light-Company ATIN:
I. R. Finfrock, Jr.
Vice President - Generation Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Gentlemen:
You were informed by our letter dated September 7, 1973, of our concern about the possibility that your control rods fabricated by the General Electric Company may have inverted poison tubes. Prior to startup following your present outage you will have completed requested shutdown reactivity margin measurements to assure an adequate shutdown margin existed at the time of the measurements. We are contii ;ing our review of this possible i
occurrence and have concluded that insufficient data exists to conclude that poison redistribution cannot occur.
Therefore, you are requested to submit j
the following information for our review:
(1) analyses of possible length and location of poison voids which could be caused by boron carbide redis-tribution, (2) the effect of such redistribution on normal operation.
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transients, and accidents, (3) proposed changes to technical specifications which will assure that all safety margins stated or implied in your FSAR j
are maintained, (4) surveillance requirements to maintain adequate shutdown i
reactivity margins and monitor changes in poison distribution,'(5) your plans and schedules for changeout of control rods, (6) expected curve of 4
reactivity vs burnup for remainder of current operating cycle, and (7) a comparison of predicted va measured criticality measurements for the 3 fuel cycles at Oyster Creek as well as a summary of the results of the control rod inventory checks required by Technical Specification 4.2.F including any corrections made to the predictions based upon previous data.
Copies of the " Reactor Control Blade Evaluation" special report and supplement submitted by The Millstone Point Company along with our reply and safety evaluation are enclosed to serve as guidance in the preparation of your submittal.
It is requested that any proposed changes within your Technical Specifications to account for poison redistribution in inverted s
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Jersey Centrkl Power
- Sept. 28,I-1973
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- poison tubes be implemented. upon submittal pending completion of our.
review of your proposed changes. Your response is requested within 90 days as three signed and thirty-seven additional copies.
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Sincerely.
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/ ff5 Donald J. S holt l,.
Assistant Director for Operating Reactors i
Directorate of-Licensing
Enclosures:
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MillstoneLitra dtd'7/23 6:7/26/73 transmitting Reactor Control-Blade Evaluation and Supplement 2.. AEC ltr to Millstone dtd 7/27/73 and Safety Evaluation cc w/ enclosures: see next page S
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Jersey Cong al fowed Light ~
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dept. 28, 1973 cc:
George F. Trowbridge, Esquire-Shaw, Pittnan, Potts, Trowbridge
- & !!adden 910 - 17 th S t ree t, 11. W.
Usshington, D. C.
20006 CPU Service Corporation
' ATTN: Mr. Thomas M. Crimmins Safety 6. Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 J. Lester Yoder, Jr., Esquire 206 Horner Street.
Toms River, New Jersey 08753 Mr. Kenneth B. Walton
-Brigantine Tutoring 309 - 21st Street, South Brigantine, New Jersey 08203 Miss Dorothy R. Horner Township Clerk Township of Ocean Waretown,'New Jersey 08753 Ocean County Library 15 Hooper Avenue Toms River, New Jersey 08753 t
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Jersey Central Power & Liglit Con 11;any M ADISON AVENUE AT PUNCH DOWL Ho AD e MORRIS T OWN, N. J. 07960 9 $ 39 611 I August 27, 1973 Mr. A. Gianbusso Deputy Director for Reactor Projects Directorat: of I.icensing United States Atomic Energy Commission Washington, D. C. 20545
Dear Mr. Giambusso:
Subject:
Oyster Creek Station Docket No. 50-219 Fuel Densification Your Ictter of August 24, 1973 requested that the Commission be inforned by I?:00 noon Eastern Standard Time today what actions have been taken to comply with the Older fo2 Mudification of License and the maximum power level attainable at the Oyster Creek Nuclear Genercting Station consistent with that Order.
Action was initiated upon receipt of your letter to adjust the core power distribution and power level to comply with the AEC Order.
The maximum g(nerating capability of the plant varies with the overall core power distribution and the fuel type which may be limiting.
This variation is presented in Table 1.
The Oyster Creek Nuclear Generating Station is currently operating at 1754 !#t (90.8%
of rated power).
Very truly yours,
,A rs i + < %
a R. H. Sims Vice President Ph At ti.chnent cc:
rec *cr9 e of Regulatory Operatiens
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TABLE 1 ALLOWABLE POWER ' LEVEL VS. GPF AT OYSTER CREEK (In Accordance with August 24, 1973 AEC Letter)
FUEL TYPE
.POWhR DMt)
GPF MAPUiGR I
10 0 1.91 10.9 KW/Ft 1960 1.94 12,800 MdD/T*
1800 2.05 1676 2.20 1582 2.33 II 1930 1.97 11.25 KW/Ft
' 6,000 F5lD/T*
1900 2.00 1800 2.11 1729 2.20 1632 2.33 III 6 IIIE**
1930 1.82 10.4 KW/Ft
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1900 1.85 1800 1.95 1600 2.20 1510 2.33
- Appraximate present fuel type average exporure.
- No cxposure dependence yet decketed for densification limitations.
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E. D. Thornburg, Chief September 28, 1973 j
l Field support & anforcement tramuk l
Directorate of hogulatory operatisme, Bg j
FACF B0 I/73-8 (AppAREBr WCotMJW GF CMrROL ktRg)
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b ad ject informatism em Syster Creek and Eine Mile Point is a==tm4 W i
la ampert ass. 50.219/73-11 and 56-220/73-06, respectively.
4 The adject infennetten for Pilgrim 1. M111stene 1 and >====e Yankee is as fo11oes:
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Plant procedures for each facility require a red compling test be made every time e red is pulled to the full est posities (match 44). A metah set oisesi is given when the red is et i
i match 48; if the rod is uneempted, the position light will l
so out and a " rod evertravel" alman is sounded.
iP toda that are partially withdress are monitored by the suelear in trimmentation to insure remetivity dange with med mottom.
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hee teste are perfemmed during each startup and weekly during i
poser operation while perfemming the red esercistag.
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Plant management is to be antified of any red uneempling.
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Operator action - If a red is femmed to be unceepted, the operator is to attempt recoupling by driving the red in ese er three notches, i
and withdrering the red to matcei 48, givtag another esepling check.
l If these attempts feil to reemaple the red, it times ausst be fully j
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imeerted, electrically dissemed, drive water testated, and the t
earms accuumalater discharged and wanted.
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Only Hilletsune i has esperiammed med emaeup112._. em 7/34/73 CE 18-35 see Sauma unsoupled. During a remeter sh-e+ em 7/26/73, c3D 18-35 une replaced eith a previamely everhauled drive. The ease emesimpiing prehlam one presset. h red une then Sally immorted and electrically 2
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form AEC lle (Rev. 943) ABCM 0240 l
- 4 H. D. Thornburg (FACF RO I/73 8 - Apparent Uncoupling of Control Rods)
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Control room operators were interviawed at each facility and all appeared to be thoroughly fantliar with the procedures in question.
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Both the QLD position indicating system and the overtravel alarm circuits were reported to have given good servios in past operations.
4 E. T. Carlson, Chief Facility Operations Branch i
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