ML20245J387
| ML20245J387 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/14/1989 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20245J377 | List: |
| References | |
| NUDOCS 8908180017 | |
| Download: ML20245J387 (4) | |
Text
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QUAD-C2T2ES DPR-29 whole body dose received from external sources shall be assigned 3
to specific major work functions.
j l
3.
Monthly Operating Report Routine reports of operating statistics and shutdown experience i
shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the appropriate Regional Office, to arrive no later than the 15th of i
each month following the calendar month covered by the report.
In addition, any changes to the ODCM shall be submitted with the Monthly Operating Report within 90 days of the effective date of the change.
A report of major change to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the onsite review function.
If such change is re-evaluated and in5ERT not installed, notification of cancellation of the change should g
be provided to the NRC.
B.
Unique Reporting Requirements 1.
Radioactive Effluent Release Report (Semi-Annual)
A semi-annual report shall be submitted to the Commission within 60 days af ter_ January 1 and July 1 of each year specifying the quantity of each of the radionuclides released to unrestricted areas in liquid and gaseous affluents during the previous 6 months.
The format and content of the report shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June, 1974 Any changes to the PCP shall be included in this report.
2.
Environmental Program Data (Annual Report)
An annual report containing the data taken in the standard radiological monitoring program (Table 4.8-4) shall be submitted prior to May 1 of each year.
The content of the report shall include:
a.
Results of-all environmental measurements summarized in the format of the Regulatory Guide 4.8 Table 1 (December 1975).
(Individual sample results will be retained at the Station).
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
Summaries, 3
interpretations, and ant. lysis of trends of the results are to
{
be provided.
$$ % 80h $$$$
rg4 6.6-2 Amendment No. 114
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INSERT-
'+;
4;
- Core Oper'ating. Limits. Report r'
a.
Core operating' limits shall'be. established and. documented in the.
CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
(1)
The Rod Withdrawal Block Monitor Upscale Instrumentation Setpoint for Table'3.2-3 of Specification 3.2.C.and for Specification 3.6.H.
-(2) The overall average of the 20% insertion' scram time data for Specification 3.3.C.
.(3). The Average Planar Linear Heat Generation Rate-(APLHGR) for Specification 3.5.I.
(4) The Linear Heat Generation Rate (LHGR)'for Specification 3.5.J.
(5) The Minimum Critical Power Ratio (MCPR) for Specification 3.5.K and 3.6.H.
(6)
The K _ core flow MCPR adjustment' factor for Specification
_ f 3.5.K.
b.
The analytical methods used to determine the core operating limits shall be:those previously reviewed and approved by NRC in-NEDE-240ll-P-A,. General Electric Standard Application for' Reactor Fuel (latest approved revision).
c.
The core operating limits shall be determined so that all applicable' limits (e.g., fuel thermal-mechanical limits, core-thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident. analysis limits) of the L
safety analysis are met.
d.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall'be provided upon issuance, for eatn reload cycle,'to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
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/J //st cl1nterif B
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QUAD-CITIES DPR-30
'2.
A tabulation shall be' submitted on an annual basis of the number of station utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job function (Note:
this tabulation supplements the requirements of Section 20.407 of 10 CFR 20), e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance). waste crocessing. and refueling.
The dose assignments to various duty functions may be estimates. based on pocket dosimeter, TLD, or film badge measurements.
Small~ exposures totaling less than 20% of the individual total dose need
~
'not be accounted for.
In the aggregate, at least 80% of the total.whole body dose received from external sources shall be assigned to specific major work functions.
3.
Monthly. Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control. U.S. Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the appropriate Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.
In addition, any changes to the ODCM shall be submitted with the Monthly Operating Report within 90 days of the effective date of the change.
A report of major change to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the onsite review function.
If such change is re-evaluated and not installed, notification of cancellation of the change should be provided to the NRC.
4.
Core Operating Limits Report a.
Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
(1)
The Rod Withdrawal Block Monitor Upscale Instrumentation Setpoint for Table 3.2-3 of Specification 3.2.C and for Specification 3.6.H.
(2) The overall average of the 20% insertion scram time data for Specification 3.3.C.
l (3) The Average Planar Linear Heat Generation Rate (APLHGR) for Specification 3.5.I.
(4)- The Linear Heat Generation Rate (LHGR) for Specification 3.5.J.
(5)
The Minimum Critical Power Ratio (MCPR) for Specification 3.5.K and 3.6.H.
(6)
The Kf core flow MCPR adjustment factor for Specification 3.5.K.
1976H 6.6-2 Amendment No.
~
QUAD-CITIES OPR-30 l
b.
The analytical methods used to determine the core operating l.
limits shall be those previously reviewed and approved by NRC in NEDE-240ll-P-A, General Electric Standard. Application for Reactor Fuel (latest approved revision).
c.
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
d.
The CORE OPFRATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
i 1976H 6.6-2a Amendaent No.
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