ML20064K087
| ML20064K087 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/14/1983 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20064K058 | List: |
| References | |
| NUDOCS 8301180297 | |
| Download: ML20064K087 (7) | |
Text
LIMITING CONDITIONS FOR OPERATICN SURVElLLANCE REQUIREMENTS 3.7 Primary Containment 4.7 Primary Containment 3.
Pressure Suppression Chamber -
3.
Pressure Suppression Chamber -
Reactor Building Vacuum Brcakers Reactor Building Vacuum Breakers a.
Except as specified in 3.7.A.3.b a.
The pressure suppression chamber -
below, two pressure suppression reactor building vacuum breakers chamber - reactor building vacuum and associated instrumentation breakers shall be operable at all including set point shall be checked times when primary containment in-forproperoperationeverythree tegrity as required. The setpoint months.
of the differential pressure instru-mentation which actuates the pres-sure suppression chamber - reactor building breakers shall be 0.5 psig.
y b.
Fro 84nd_fterthedatethatoneof the pressure suppression chamber -
reactor building vacuum breakers is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such vacuum breaker is sooner made operable, provided that the repair procedure does not violate primary containment integrity.
4.
Drywell-Pressure Suppression 4.
Drywell-Pressure Suppression Chamber Vacuum Breakers Chamber Vacuum Breakers a.
When primary containment is a.
Periodic Operability Tests required, all drywell-pressure suppression chamber vacuum breakers shall be operable except during testing and as stated in Specifications 3.7.A.4.b, c and d, below.
Drywell-pressure suppre nion chamber vacuum breakers s4pil be considered operable if:
(1) The valve is demonstrated to (1) Once each month each drywell-pressure open with the applied force of suppression chamber vacuum breaker the installed test actuator as shall be exercised and the operability indicated by the position of the valve and installed position switches and remote position indicators and alarms verified.
indicating lights.
(2) The valve shall return by (2) A drywell to suppression chamber dif-gravity when released after ferential pressure decay rate test being opened by remote or shall be conducted at least every 3 manual means, to within 3/32" months.
of the fully closed position.
(3) Neither of the two position alarm systems which annunciate on Panel C-7 and Panel 905 when any vacuum breaker opening exceeds 3/32", are in alarm.
8301180297 830114 156 PDR ADOCK 05000293 J
SURVE11,1.ANCC REOUTREMENTS
[1MITINC CONDITIONS FOR OpEP.ATION 4.7 Primor; containment 3.7 Primary containment e
b.
During each refueling outage:
b.
Any drywell-suppression chanhcr vacuum breaker may be non-fully closed as determined by the position switches (1) Each vacuum breater shall be tested to determine that the disc opens freely provided that the drywell to suppres-to the touch and returns to the closed sion chamber dif f erential decay rate is demonstrated to be not greater than position by gravity with no in6f ea-25% of the differential pressure decay tion of binding.
ratefortheagximumallovablebypass area of 0.2 ft (2) Vacuum breaker positien switches and installed alarm systems shall be P.cactor operation may continue pro-calibrated and functionally tested.
c.
vided that no nore than 2 of the dry-well-pressure suppression chamber
'(3) At least 25% of the vacuum breakers vacuum breakers are determined to be shall be visually inspected such that inoperable,provided that they are all vacuum breakers shall have been secured or known to be in the closed inspected following every fourth re-fueling outage.
If deficiencies are position.
found, all vacuum breakers shall be d.
If a failure of one of the two in-visually inspected and deficiencies corrected.
stalled position alarm systems occurs for one or more vacuum breakers, reactor operation may centinue pro-(4) A drywell to suppression chanber Icah rate test shall demonstrate that the vided that a differential pressure decay rate test is initiated immedi-differential pressure decay rate does
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ately and performed cvery 15 days there-not exceed the rate which would occur af ter until the f ailure is corrected.
through a 1 inch orifice without the The test shall meet the requirements addition of air or nitrogen.
of Specification 3.7.A.4.b.
5.
Oxygen Concentration
- 5., Oxygen Concentration
,The primary containment oxygen concen-tration shall be measured and recorded c.
After completion of the startup test at least t#Fbe deckly.
program and demonstration of plant electrical output, the primary con-tainment atmosphere shall bc reduced to less than 5% oxygen by volume with nitrogen gas during reactor power operation with reactor coolant pres-sure above 100 psig, except as specified in 3.7.A.S.b.
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BASES:
3.7.A & 4.7.A Primary Containment (Cont'd) margin of safety for the primary containment in the event of a small break in the primary system.
Each drywell suppression chamber vacuum breaker is equipped with three switches. One switch provides full open indication only. Another switch provides closed indication and an alarm on Panel C-7 should any vacuum breaker come off its closed seat by greater than 3/32". The third switch provides a separate and redundant alarm on Panel 905 should any vacuum breaker ome off its closed seat by greater than 3/32". The two alarms above are those referred to in Section 3.7.A.4.a(3) and 3.7.A.4.d.
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168a
Attachm:nt B Pr3 posed Technical Specification Change Proposed Change Reference is made cc Pilgrim Nuclear Power Station, Unit #1 Technical Specification, Appendix A, Section 3.3.B
" Control Rods", Item 3.3.B.5, Remove the followin9:
Item 3.3.B.S.c "1.06" Add the following:
Item 3.3.B.S.c
...will remain above "the Safety Limit MCPR" assuming a single...
Reason for Change In Item 3.3.B.5.c, reference is made to an MCPR of 1.06.
From the basis it is clear that this re/ers to the Safety Limit MCPR. When retrofit fuel was loaded intc the core during Reload 4, the Safety Lir..it was changed to 1.07 in Specifica-tion 1.1. A and other references to MCPR of 1.06 were replaced by " Safety Limit MCPR".
Item 3.3.B.5.c was apparently overlooked.
Safety Considerations This change does not present an unreviewed safety que:t;on as defined in 10 CFR 50.59(c).
It has been reviewed and approved by thc Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.
Schedule of Change This change will be put into effect upon receipt of approval by NRC.
Fee Determination Pursuant to 10 CFR 170.22, Boston Eaison Company proposes this change as Class II.
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.B. Control Rods 4.3.B. Control Rods 4.
Control rods shall not be with-4.
Prior to control rod with-drawn for startup or refuelira
- drawal for startup or unless at least two source range during refueling, verify channels have an observed count that at least two source rate equal to or greater than range channels have an three counts per second, observed count rate of at least 'bree counts per 5.
During operation with limiting second.
control rod patterns, as deter-mined by the Reactor Engineer, 5.
When a limiting control rod either:
pattern exists, an instru-ment functional test of the a.
Both RBM channels shall be RBM shall be performed operable: or prior to withdrawal of the designated rod (s) and b.
Control rod withdrawal shall daily thereafter.
be blocked: or c.
The operating power level shall be limited so that the MCPR will remain above the Safety Limit MPCR assuming a single error that results in complete withdrawal of any single operable control rod.
C.
Scram Insertion Times C.
Scram Insertion Times 1.
The average scram insertion 1.
Following each refueling time, based on the deener-outage, each operable gization of the scram pilot
<> control rod shall be sub-
.o valve solenoids as time zero, jected to scram time tests of all operable control rods from the fully withdrawn in the reactor power ppera-position.
If testing is tion condition shall be no not accomplished with the greater than:
nuclear system pressure above 950 psig, the d""'
% Inserted Average Scram measured scram insertion From Fully Insertion time shall be extrapolated Withdrawn Times (set) to reactor pressures above 950 psig using previously 10
.55 determined correlations.
30 1.275 Testing of all operable
[
50 2.00 control rods shall be com-l 90 3.50 pleted prior to exceeding 40% rated thermal power.
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83
Attachment C Proposed Technical Specification Change Proposed Change Reference is made to Pilgrim Nuclear Power Station, Unit #1 Technical Specifica-tion, Appendix A, Section 6.9, " Reporting Requirements", Item 6.9.A.2.
Remove the following:
Item 6.9.A.2 "a monthly basis... appropriate Regional Office,"
Add the following:
Item 6.9.A.2
... be submitted on "a monthly basis to Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D. C.
20555," to arrive no...
Reason for Change The reporting requirements of Item 6.9.A.2 presently reflects the guidance specified in USNRC Regulatory Guide 10.1, " Compilation of Reporting Require-ments for Persons Subject to NRC Regulation", Revision 3, dated May 1977.
This change is proposed to reflect reporting guidelines specified in USNRC Regulatory Guide 10.1, Revision 4, dated October 1981.
Compliance with the latest revision to this Regulatory Guide will assure timely and correct distribution of this report in accordance with the provisions of Title 10, Chapter 1, Code of Federal Regulations.
Safety Considerations This change does not present an unreviewed safety question as defined in 10 CFR 50.59(c).
It has been reviewed and approved by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.
Schedule of Change This change will be put into effect upon receipt of approval by NRC.
Fee Determination Pursuant to 10 CFR 170.22, Note 2 Boston Edison proposes this change be exempt from any fees, as it will be issued for the convenience of the NRC.
a 2.
Monthly Operating Report. Routine reports of operating statistics, shutdown experience and forced reductions in power shall be sub-mitted on a monthly basis to Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Comnission, Washington, D.C.
20555, to arrive no later than the 15th 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.
Occupational Exposure Tabulation. A tabulation of the number of strtion, utility and other personnel (including contractors) re-ceiving exposures greater than 100 mrem /yr and their associated man-rem exposLre according to work and job functions, e.g. reactor operations and surveillance, inservice inspection, routine mainten-ance, special maintenance (including a description), waste processing, and refueling shall be submitted on an annual basis.
This tabulation supplements the requirements of 20.407 of 10 CFR 20. The dose assign-ment to various duty functionfumay be estimates based cn pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individuad 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.
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