ML20023B762
| ML20023B762 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/22/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20023B759 | List: |
| References | |
| NUDOCS 8305060279 | |
| Download: ML20023B762 (8) | |
Text
_
M
%q%
UNITED STATES p
c; NUCLEAR REGULATORY COMMISSION s
a wasnimaron. o. c. asses
~
BOSTON EDISON COWANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDPENT TO FACILITY OPERATING LICEN,TE 4
Amendment No. 68 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has f und that:
A, The application for amendment by the Boston Edison Company (the licenses) dated January 14, 1983 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; B.
The facility will operate in conformity with the appifcation, the provisions of the Act, and the rules and regulations of the 1
Commission; C.
There is reasonable assurance (f) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in ecmpliance with the Conunission'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.
1 2.
Accordingly, the license is amended by changes to the Technical Spec-Ifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No. DT4R-35 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as re-vised througn Amendment No. 68, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8305060279 830422 PDR ADDCK 05000293 p
.=.
A 2
s v
3.
This license amendment is effective as of the date of issuance.
I' FOR THE NUCLEAR REGULATORY COMMISSION 1
Domenic B. Yassallo, Chief
.s Operating Reactors Branch #2 Division of Licensing 1
)
Attachment:
Changes to the Technical l
Speci fications Date of Issuance:
April 22,1983
..~
,g 1
)
%.. D g
i i
e mer e
4 0
e l
e n
i
?
0
e r..,
-? 'k -
w 1
t
~.
_ s i(
.o.
s
,.S ATTACHMENT TO LICE!!SE AMENDMENT NO. 68 s--
~
FACILITY OPGATING LICENSE NO. OPR-35
)'
.. e I.'-
DOCKET 9 41 50-293 e
s
,v
,__ Ecplace the following pages of the Appendix "A" Technical Specifications with s the gnclosed pages.
The revised pages are identified by Amendment Number and
' contain a vertical line indicating the area of.,ch,ange.
7 REMOVE INSERT 83 83 t
- 155, 156 157 157 168a 168a
- ~
218
/
218
/
A o
7
+
t'
\\
[. 's f
4 y
4, v
y
, ' mL Y
\\
s e '
9
,.,. s,"-
~
+
\\
'w.
('
N 4s 5
g 3g A
g Q
,n
\\'\\
.,[\\ ~
~.
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.B. Control Rods 4.3.B Control Rcds 4.
Control rods shall not be with-4.
Prior to control rod with-drawn for startup or refueling 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.
observad count rate of at least three counts per 5.
During octration with limitin9 second.
control rod patterns, as deter I 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 red withorawal 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 scras insertion 1.
Following each refueling time, based on the deener-outage, each operable gization of the scram pilot control rod shall be sub-valva solenoids as time zero, jected to scram time tests of all operable control rods from the fully withdrawn in the reacter power opera-position.
If testing is tion condition shall be no not accomplished with the greater than:
nuclear system pressure above 950 psig, the
% Inserted Average Scram measured scram insertion From Fully Insertion time shall be extrapolated Withdrawn Times (set) to reactor pressures above j
950 psig using previously 10
.55 determined correlations.
30 1.275 Testing of all operable 50 2.00 control rods shall be com-90 3.50 pleted prior to exceeding 40% rated thermal power.
Amzndment No. 75 68 83
-. =
LIM!i1NG C.ONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 Primary Containment 4.7 Primary Centainment I
3.
Pressure Suppression Chamber -
3.
Pressure Suppression Chamber -
Resctor Building Vacuum Breakers 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 4
chamber - reactor building vacuum and associated instrumentation breakers shall be operable at all including set point shall be checked times when primary containment in-for proper operation every three 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.
i b.
From and after the date that one of the pressure suppression chamber -
)
reactor building vacuum breakers is made or found to be inoperable for any reason, renctor 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 prima y containment integr;ty.
4 Drywell-Pressure Suppression 4.
Drvwell-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 suppression chamber vacuum breakers shall be considered operable if:
(1) The valve is demonstrated to (1)
Once 'ach month each drywell-pressure e
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 alams verified.
indicating lights.
(2) ~he valve shall return by (2) A drywell to suppressicn 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.
i Amendment No. 68 156
_1
4 f_TMTTTMf" (*0"DITf 0'fS FOR OPERATION SUPVE17,1. ant"E REOUIREMENTS 3.7 Primary ecctninment 4.7 Prsmary containment 1
b.
Any dryvell-supptcztion chamber vacuum b.
During each refueling outage b74aker may be non-fully closed as l
determined by the position switches (1) Each vacuum bre:her shall be tested to provided that the drywell'to suppres-determine that the disc opens freely sion chamber differential decay rate to the touch and returns to the closed l
1s demonstrated to be not greater chan position by gravity with no indica-
~
25% of the differential pressure decay tion of binding.
rateforthemyimumallocablebypass j
area of 0.2 ft.
(2) Vacuum breaker position switches and installed alarm systems shall be j
calibrated and functionally tested.
{
c.
Reactor operation may continue pro-vided that no more than 2 of the dry-l well-pressure suppressica chamber
- (3) At least 25% of the vacuum breakers vacuum breakers are determined to be shall be visually inspectsd such that d
inoperable previded that they are all vacuum breakers shall have been
]
secured or known to be in the closed inspected following every fourth re-l position.
fueling outage. If deficiencies are found, all vacuum breakers shall be d.
If a failure of one of die two in-visually inspected and deficiencies.
stalled position alarm systems occurs corrected.
for one or more vacuum breakers, l
reactor operation may continua pro-(4) A drywell to suppression chamber lesh vided that a differential pressure rate test shall demonstrate that the decay rate test is initiated immedi-
- differential pressure deca ~y rate does a
ately and per(ormed every 15 days cliere-not exceed the rate which would occur after 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.
Oxyren concentration
+
l S., Oxynen Concentration
,The primar/ containment oxygen concen-a.
.After completion of the startup test tration shall be measured and recorded program and demonstration of plant at least twice seekly.
)
electrical output, the primary con-l tainment atmosphere shall be reduced i
to less than 5% oxygen by volume with microgen gas during reactor power l
operation with reactor coolant pres-sure,above 100 psig, except as specified in 3.7.A.5.b.
1 l
l 157 t
l Amendment No. 68
~
g,
1 BASES:
3.7.A & 4.7.A Primary Containment (Cont'd) margin of safety for the primary con?.ainment 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 4
breaker come off its closed seat by greater than 3/32". The third switch provides a separate and redundant alarm on Panel 905 snould any vacuum breaker come 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.
i 1
i l
a J
i 1
1 Amendment No. 68 168a-J
.,m.
2.
Monthly Operating Repor*, Routine reports of operating statistics, shutdown experience and forced reductions in pcwer shall be sub-mitted on a monthly basis to Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, 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 fc.cility, including safety-related maintenance, for the monthly report period. -
3.
Occupational Exposure Tabulation. A tabulation of the number of station, utility and other personnel (including contractors) re-ceiving exposures greater'than 100 mrem /yr and their associated man-rem exposure acccrding to work and job functions, e.g. reactor operations and surveillance, inservice inspection, routina 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 functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small cxposures totalling 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.
~
218 (the next.page is 220)
Amendment No. 3g 68
~