ML20077E936
| ML20077E936 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/05/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077E934 | List: |
| References | |
| NUDOCS 9106110307 | |
| Download: ML20077E936 (4) | |
Text
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WASHINGTON o C. 20%5 SAFETY EVALUATION RY THE OFFICE OF NUCLEAR REACTOR REr,UL ATION REL ATED TO AYENDMENT NO. i s.,
,TO PROVISIONAL OPERATINr. LICENSE NO. DPR-16 r.pU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER 4 LTr,HT C MPANY OYSTERCREEENUCLEARr.ENERATINr.STATg DOCKET NO 50-?l9
1.0 INTRODUCTION
9y an applic) tion for an amendment dated November 19, 1990, GPU Nuclear Cor-poration reauested a revision of the Ovster Creek Nuclear Generating Station Technical Specifications (TS) surveillance intervals for Table 4.1.1 The proposed amendment modifies the calibration interval for High Reactor Pressure.
Low Reactor Water level, low-Low Reactor Water level, and High Water level in Scram Discharge Volume.
An editorial chinge to correct the bases for the control function of the Hioh Drywell Pressure Trip System in TS section 3.1 is also proposed.
2.0 EVALUATION As currently shown in the bases of Oyster Creek Nuclear Generating Station TS Section 3.1, a High Drywell Pressure Trip includes reactor isolation as a High Drywell Pressure Trip function.
The licensee stated that reactor isolation is not initiated by a High Drywell Pressure Trip and the bases is in error.
The proposed change removes the reference to reactor isolation from the bases for the Hioh Drywell Pressure Trip referenced in TS 3.1.
This change is acceptable to the staff.
The licensee also proposed changes to TS Table 4.1.1, item 1 - High Reactor Pressure, Item 3 - Low neactor Water Level, and item 4 - Low-low-Reactor Water Level.
The present calhration interval for these instrument channels is specified as at least once per 3 months.
The proposed TS change revises the calibration interval to 12 months and meintains the instrumentation testing interval at once per month by removing the reference to Note 1 on Table 4.1.1.
To justify the calibration interval extension, the licensee reviewed the as-found and the as-left calibration data from plant instrumentation surveillance and maintenance records, ensuring that no adverse trends were present.
The licensee also utilized the plant data to determine plant-specific drift values for the subject instrumentation.
The plant-specific drif t values were then determined for a bounding calibration interval of 12 months for each instrument.
The licensee then performed a comparison of the projected instrument drift with the drift values presently incorporated 9106110 w 010605 FDR ADOCK 050UOM
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into the setpoint analysis.
The licensee determined that the plant-specific drift values were bounded by the values in the setpoint calcul6tions and no revision to setpoints, safety limits, or safety analysis assumptions were required.
Durina a February 27, 1991 telephone conversation the licensee stated thdt the Oyster Creek Nuclear Generatinq Station setpoint methodology used to determine drift values and to verify the setpoint calculations endorsed Regulatory Guide 1.105 and ISA A67.04-198?.
Additionally, the vendor data for the analog instruments is specified to remain below the drift value utili7ed in the Oyster Creek Nuclear Generating Station setpoint calculations for a period of 30 months.
This interval is well within the 12-month calibration interval proposed by the licensee.
A daily channel check is performed on these instruments and is not being revised by this TS revision.
The licensee is revising Note 3 of Table 4.1.1 to specify a 12-month calibration interval for the high reactor pressure, low reactor water level, and low-low water level transmitters.
Note 3 will also specify that the electronics, and bistable trips will be tested by the injection of an external test current at the previous once every 3 month interval requirement.
Rased on our review of the proposed change, the staff finds the revised calibration frequency for this instrumentation acceptable.
Table 4.1.1 Item 5b - High Water in the Scram Discharge Volume is also being revised by the licensee to reflect modifications that provided for both digital and analog trip instrumentation.
The analog instrumentation calibration interval is being evtended from once every 3 months to once per year.
The licensee performed a review of the Scram Discharge Volume analog instrumentation surveillance calibration data and confirmed that the instrument drif t for the analog instrumentation will remain within acceptable limits for the proposed yearly calibration interval.
The licensee stated that over 6 years of data was available for the evaluation of these instruments.
Additionally, Note 3 of Tal)le 4.1.1 requires the testing of the electronics and output bistables once every 3 months by the injection of an external test current.
A monthly functional test is also reouired for the High Water level in Scram Discharge Volume instrumentation and is not being revised by the licensee.
Based on the above, the staff finds the proposed calibration interval extension for the High Water Level in the Scram Discharge Volume analog instrumentation to be acceptable.
Table 4.1.1 Item 27a - Scram Discharge Volume Water Level High, analog rod block calibration interyal is being revised from the preser,t once por 20 months interval to once each refueling outage.
This change results from calculations performed by the licensee based on surveillance test results documented since the instrumentation modifications were installed during the refueling outage of 1983-1984 The evaluation determined that the Scram Discharge Volume Water Level High, analog rod block instrumentation drif t data would support an extended calibration interval of once per refueling outaae (nominally 24 months).
The remarks section of item 27a is also revised to limit varying the level in the sensor column to ulibration only.
The functional test will continue to test the Scram Discharge Volume Water Level High, analog rod block, instrumentation electronics once very 3 months by the injection of a simulated test signal.
The staff finds the proposed changes to Table 4.1.1, item 27a Scram Discharge Volume Water Level High, analog rod block instrumentation to be acceptable.
_ (
The charge to TS Table 4.1.1 Item Ea - High Water 1evel In The Scram Discharge a
Volume Digital Scran resised the functional tes El frch once per nonth j
based on Not e 1 of Table 4.1.1 to once per 3 months.
The calibration interval will cent...ue to be once every 3 months.
The licensee stated that a test intersal of enre every '.onths will ensure operation within acceptable drift limics.
The licensee also stated that incorporation of TS changes to Table 4.1.1 Items f>a, Eb, and 27a (Scram Discharge Volume instrumentation) will significantly i
reduce the ren-ren exposure on the instrument and control technicians for these surveillances.
A steff review of the abc changes found them to be consistent with the Standard Technical Specification
,STS) and similar plant TS.
Eesed on tne above, the staff tinds the preposed change to revise the surveillance requirements of Tetle 4.1.1, Item 5a to once every 3 nonths to be acceptable.
i The surveillance history evaluation performed by the licensee reviewed the t
as-found, as-left calibration data for the referencec protective instrumentation.
Plant-specific drif t values were determined and compared to the values inccrporated into the Oyster Creek f:uclear Gev ra+ing Station setpoint calculations, lne licensee provided additional information on the methodology used to determine the plant-specific drift values based on the revised surveillancc intervals. The licensee detr ined that the projected drift values were bounded by the present setpoi:
analysis.
Vendor drift data referenced by the licensee for hign reactor pressure, low reactor water level, and low-low reactor water level is also specified to remain below the drif t value utilized in the Oyster Creet t:uclear Generating Station setroint calculations. The revision to the Scrcm Discharge Volume calibration intervals will clso reduce the current ran-rem burden of the plant instrument and control technicians.
The licensee will continue to collect and trend the necessary data to ensure that an extended surveillance interval remains appropriate for the referenced instrumentation. The staff is currently reviewing the Oyster Creek Nuclear Generating Station setptint methodology (Standard ES-002 Instrument Error Calculation and Setpoint Determination TAC 69012) which includes Oyster Creek setpoint calculations referenced in this submittoi.
Should th:o task determine that the Oyster Creek setpoint methodology requires re-evaluation, it is expected that the licensee will review the affected surveillerce intervals as required.
Based on the ebove, the staff finds the proposed surveillance interval extensions te be acceptable.
3.C STATE CONSULTAT_ ION in accordan'e with the Commission's regulations, the New Jerrey State officiel was notitied of the proposed issuance of the amendment. The State official had no comments.
4' ENVIR0 tit 1EtlTAL C0tiSIDERATION Pursuant to 10 CFR 51.21, 51.32 and 51.35, an environmental assessment and finding of no significant impact have been prepared and published in the FEDERAL REGISTER on June 5, 1991(56 FR 25700
).
Accordingly, based upon the
. environmental assessment, we have determined that the issuance of the amendment will not have significant effect on the quality of the human environment.
5.0 CONCL!!SION The Commission has concluded, based on the consideraticas discussed above, that:
(1) there is reasonable assurance thet the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense.and security or to the health and safety of the public.
Principal Contributor:
C. Doutt Date: June 5, 1991 a