ML20236N444
| ML20236N444 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/05/1987 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236N449 | List: |
| References | |
| NUDOCS 8708110504 | |
| Download: ML20236N444 (6) | |
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y[f UG!/ h, UNITED STATES y % g) a / a j 3ci g NUCLEAR REGULATORY COMMISSION 3
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WASHINGTON, D. C. 20555 x,,.* f BOSTON EDISON COMPANY 00CMET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE l
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Amendment No. 103 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Boston Edisnn Company (the licensee) dated February 18, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the l
Commissioa; C.
There is reasonable assurance (i) that the activities authorized by l
this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicatet in the attachment to this license amendment and Paragraph 3.B. of Facility Operating License No. DPR-35 is hereby amended to read as follows:
3708110504 870805 PDR ADOCK 05000293 P
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, (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.103, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications..
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Victor'Nerses, Acting Director Project Directorate I-3 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 5, 1987
l ATTACHMENT TO LICENSE AMENDMENT NO.103 l
l FACILTIY OPERATING LICENSE NO. DPR-35 I
DOCKET NO. 50-293 Replace the following pages of the Appendix "A" Technical Specifications with 1
the enclosed pages.
The revised page is identified by amendment number and
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contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Pages Insert Pages 59 59 218 218 I
223 223 I
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.c Notes for Table 3.2.r i
(1)
With less than the minimum number of instrument channels, restore the inoperable channel (s) within 30 days.
(2)
With the ins'rument channel (s) providing no indication to the control room, restore the indication to the control room within seven days.
(3)
If the requirements of notes (1) or (2) cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown Condition with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(4)
These surveillance instruments are considered to be redundant to each l
other.
(5)
At a minimum, the primar y or back-up* parameter indicators o.all be l
operable for each valve when the ' valves are required to be operable.
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With both primary and backup
- instrument channels inoperable either j
return one (1). channel to operable status within 31 days or be in a l
shutdown mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The following instruments are associated with the safety / relief and safety valves:
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Primary Secondary l
Valve Acoustic Monitor Tall Pipe Temperature Thermocouple j
203-3A ZT-203-3A TE6271 203-3B ZT-203-3B TE6272 203-3C ZT-203-3C TE6273 203-30 ZT-203-30 TE6276 203-4A ZT-203-4A TE6274-B 203 4B ZT-203-4B TE6275-8
- See Note (6)
(6)
At a minimum, for thermccouples providing SRV tail pipe temperature, one of the dual thermocouple will be operable for each SRV when the valves are required to be operable.
If a thermocouple becomes inoperable, it shall be returned to an operable condition within 31 days or the reactor shall be placed in a shutdown mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(7)
With less than the minimum number of operable instrument channels, restore the inoperable channels to operable status within 7 days or prepare and submit a special report to the Commission within 14 days l
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of the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the channels to operable status.
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' Amendment No. 83, 103 59
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6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10. Code of-Federal Regulations. the following identified reports shall be submitted
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to the Commission.
A.
Routine Reports l
1.
Startup Report.
A summary report of plant startup and power I
escalation testing snall be submitted following (1) receipt of an operating 11 cense,.(2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel i
supplier, and (4) modifications that may have significantly altered the nuclea'r, thermal, or hydraulic performance of the plant.
The I
report shall address each of the tests identified in the FSAR.and shall in general include a description of the measured values of.th operating' conditions or characteristics obtained during the test program and a comparison of these values with design predictions ano specifications, Any corrective actions that were required to obtain i
satisfactory operation shall also be described.
Any additional i
specific details required in license conditions based on other 1
commitments shall be included.In this report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 l
months following initial criticality, whichever is earliest.
If the j
Startup % port does not cover all three events (i.e., initial criticality, completion of startup test program,-and resumption or i
commencement of commercial power operation), supplementary reports I
shall be submitted at least every three months until all three events have been completed.
2.
Monthlv Operating Report.
Routtne reports of operating statistics, shutdown experience and forced reductions in oower shall'be submitted on a monthly basis to the Commission to arrive no later than the 15th l
of each month following the calendar month covered by the report.
The Monthly Operating Report shall include a narrative summary of operating experience that describes the operation of the facility, including safety-related maintenance, for the monthly report period.
3.
dcupational Exposure Tabulation.
A tabulation 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 functions, e.o. reactor operations and surveillance inservice inspection, routine i
maintenance, special maintenance (including a description), waste 4
processing, and refueling shall be submitted on an annual basis.
This tabulation supplements the requirements of 20.407 of 10 CFR 20.
The dose assi'gnment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 207. of the individual total dose need not be accounted for.
In the aggregate, at least 807. of the total whole body dose received from external sources shall be assigned to specific major work functions.
Amendme m No. 30, EB, EB, 103 (the next page is 220) 218 Asweld $7 +10-J& TrK
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l 6.9.C.
Uniave Reporting Requirements 1.
Radioactive Effluent Release Report A report snall be submitted to the Commission within 60 days after January 1 and July 1 of each year specifying the quantity of eacn of the principal radionuclides released at and beyond the site boundary in liauld and gaseous effluents during the previous 6 months.
The format and content of the report shall be in accordance with Appendix
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B of Regulatory Guide 1.21 (Revision 1) dated June. 1974.
i 2.
Annual Radiological Environniental Monitoririg Report I
A report on the radiological environmental surveillance program for j
l the previous calendar year of operation shall be submitted to the l
Commission prior to May 1 of the year.
The reports shall include l
l summaries, interpretations, and statistical evaluation of the results l
of the radiological environmental surveillance activities for the l
report period, operational controls and previous environmental i
surveillance reports, and an assessment of the observed impacts of l
the plant operation on the environment.
The reports shall also include the results of any 1and use surveys which affect the choice of sample locations.
If harpful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem, l
l The Annual Radiological Environmental Monitoring Report shall include a summary of the results of analysis of all radiological i
environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified.in the l
table and figures in the Offsite Dose Calculation Man'ual (00CM) as l
well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some results are not available prior to May 1 of the year, the report shall be submitted, noting and explaining the j
reasons for the missing results.
The missing data shall be submitted
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as soon as possible in a supplementary report.
The report shall also include the following:
a summary descri.ption l
of the radiological environmental monitoring program; at least two i
legible maps' covering all sampling locations keyed to a table l
giving distances and directions from the centerline of the reactor; 1
One map shall co.er stations near *.he site boundary; a second shall include the more distant stations.
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Amendment No. 23. f//, H,103 L
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