ML20090D298
| ML20090D298 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/02/1975 |
| From: | Carroll J JERSEY CENTRAL POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| AO-50-219-75-15, NUDOCS 8302250485 | |
| Download: ML20090D298 (4) | |
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James P. O'Reilly Directorate of Fogulatory operations Region I 631 Park Avenuo d
King of Prussia, Pennsylvania 19406 I.l L
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Jersey Central Power & Light Corpany
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Oyster Creek Nuclear Generating Station Docket 450-219 efi Forked River, New Jersey C4731
SUBJECT:
Abnormal occurrence Esport No. 50-219/75/15 P
The following is a prolininary report being e
i stunitted in ecepliance with the Technical Specifications, paragraph 6.6.2.
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sitial Telephone Date of sport Dates 5/30/75 Occurrences 5/30/75 sitial Written Time of sport Date:
6/2/75 Occurrences
?400 OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, KDt JERSEY 08731 Abnormal Occurrence Report No. 50-219/75/15 eZNTIFICATION Violation of Technical Specifications, paragraphs 2.3.1.a
' OCCURRENCE:
~ and 2.3.2.a which specifies limiting safety system settings for the APRM scran and rod block.
This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15A.
WDITICSS PRIOR X Steady State Power Routine Shutdown OCCUPJChCE:
Hot Standby Operatica cold Shutdevn Load Changes During Rofueling Shutdevn Routine Power Operatica P.outine Startup Other (Specify)
Operation Powers Core,1370 Hbf Electrie, 448 Flows Recirculation, 47.7 X 10 liri/h D
Feedwater, 4.99 K 10 licz/hr e
Reactor Pressures 1020 psig 8,740 mei/see Stack Gas ECRIPTICti OF On May 30, 1975, a full set of TIP traces was collected and
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calculations were performed to evaluate Coro nemal Hydraulic Paramters. %c calculations indicated that peaking factors in A
one (1) core locaticn was in excose of the values of PFe given in Technical Specification 2.1.A.1.
It was then determined that the 7J'RM scram and rod block settings were not in accordance witJ
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Specifications 2.3.1.a and 2.3.2.a.
Details are as~follows:
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.boormi occurrence aport No. 50-219/75/15 Page 2 Core Fuel Peaking PF Required Settings Actual Settings, Iocation M
Factor Scram Bod Block scrats Fod Riock 27-10*
IIIE 2.92 2.74 88s 73.96%
89.7%
80.0%
Upon discovery, corrective action was initiated to return th'e APRM settings to the required values. his was acco:::plished by inserting two (2) groups of control rods and lowering the APEM scram and rod block settings per Specifications 2.3.1.a and 2.3.2.a.
Further nargin was then obtained by increasing reactor power.
- 21s is a monitored core location, indicative of the perfor::ance of three (3) additional fuel asser.blics.
PPATCTP cat:3E Design Procedure F OCCURRE:JCE:
V.anufacturo Unusual Service Condit. ion Installation /
Inc. Envircemental Construction Co::ponent railure CTorator X Other (Specify)
License Restrictions.
e The peaking factors specified for Cycle v Operation are Icwer than all previous Technical Specification limits. It is difficult to obtain operating control rod patterns which, at low power, l
will result in operation within the required limits.
IALYSIS OF Total peaking factor is, in idself, not an indication of the b
Core Thornal Performnce. %e limits specified in the Technical l
Specifications were used for ovaluating the effet.ts of abnor=al operating occurrences and for formulation of a safety limit curvo (Tbchnical Specification Figure 2.1.1). We para: meters which are truly indicative of the coro perfor=ance are: 1) average pla: ar i
Linear heat generation rate, 2)
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rate, 3) critical pcuor ratio, and 4) assestly averaged p:nrer-void relationship. All of these parameters were within the conservativo limits specified by the Technical Specificatiens.
De critical power ratio was determined to be 2.488 for the asse:bly<
We We' APRM stir.tz was set at 89.7% of rated power cr 1731 SMt.
safety limit associated with the actual power distribution in the assembly (ie. the power level at dich the CPR = 1.37) was cal-
'The APRM screJa culated to be 1.82 X operating power or 2502 PMt.
was set at 69% of the safety limit and was therefore fully adequate-to protect against the occurrence of a critical heat flux during anticipated transients.
It may be concluded that, in this case, the total peaking factor limits are not required to protect the reactor core.
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