ML20011E943
| ML20011E943 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/12/1990 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011E944 | List: |
| References | |
| GL-89-14, NUDOCS 9002230167 | |
| Download: ML20011E943 (5) | |
Text
i
[
'.f#
%c UNITED $TATES
, ' N', a f',,g 5
flUCLEAR REGULATORY COrdfdlSSION f
wAssisciow. o. c. rosss
....+
i BOSTON EDISON COMPANY l
DOCKET NO. 50-293 I
PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.128 License No. DPR-35
]
1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found I
that.
A.
The application for amendnient filed by the Boston Edison Company 1
(the licensee) dated December 7, 1989 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 1; C.
The facility will operate in conformity with the application, the provitions of the Act, and the rules and regulations of the Cornission; C.
There is reetcnable assurance: (i)thattheactivitiesauthorizedby this eicndment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliarn-with the Comission's regulations set forth in 10 CFR Chapu D.
The issuence of this anendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuence of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have beEn satisiicC.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby emended to read as follows:
Technical Specifice.tions l
The Technical Specifications contained in Appendix A, as revised through Amendment No.129, are hereby incorporated in the license.
The licer.see shall operate the facility in accordance with the Technicel Specifications.
9002230167 900213 P
DR ADOCK 05000p93:+
p PNV L
. +
, v.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Richard H. Wessman, Director Project Directorate 1-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Attachment:
Chenees to the Technical Specifications Date of issuance:
February 12, 1990 1
a t
s ATTACHMENT TO LICENSE AMENDMENT NO.128 i
FACILITY OPERATING LICEliSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove insert 5a 5a Sb Sb i
i t
l.0 DIDEU10KS (continued)
U.
Surveillance Freauency - Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
The Surveillance Frequency establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance schedule and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Definition "U" is based on engineering judgment and the recognition that the most probable result of any particular $Urveillance being performed is the verification of conformance with the Surveillance Recuirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
V.
Surveillance Interval - The surveillance interval is the calendar titre between surveillance tests, checks, calibrations, and examinations to be performed upon an instrument or component when it is required to be operable. These tests may be waived when the instrument, component, or system is not required to be operable, but the instrument, component, or system shall be tested prior to being declared operable. The operating cycle interval is 18 months and the 25',. tolerance given in Definition "U" is applicable.
H.
Fire Suporession Water System - A fire suppression water system shall consist of:
a water source (s); gravity tank (s) or pump (s);
and distribution piping with associated sectionalizing control or isolation valves. Such valves shall include hydrant post indicator valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or spray system riser.
X.
it.Aggered Test Basis - A staggered test basis shall consist of:
(6) a test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into D equal subintervals; (b) the testing of one system, subsystem, train or other designated components at the beginning of each subinterval.
Y.
52urce Check - A source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive
[
source.
Amendment Ho. 42. EP, 128 Sa s
7 i
[
1.0 DEFINITIONS (Continued)
Z.
Offsite Dose Calculation Manual (ODCM) - An offsite dose calculation manual (ODCM) shall be a manual containing the current methodology and parameters to be used for the calculation of offsite doses due to radioactive gaseous and liquid effluents, the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints, and the conduct of the Radiological Environmental Monitoring Program.
AA.
Action - Action shall be that part of a specification which prescribes remedial measures required under designated conditions.
BB.
Member (s) of the PublicI - Member (s) of the public shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does j
include persons who use portions of the site for recreational, occupational or other purposes not associated with the site.
CC.
Site Boundarvi - The site boundary is shown in Figure 1.6-1 in the FSAR.
DD.
Radweste Tre.strent System 1.
Gaseous Radwaste Treatment System - The gaseous radwaste treatment system is that system identified in Figure 4.8-2.
2.
Licuid Radwaste Treatment System - The liquid radwaste treatment system is that system identified in Figure 4.8-1.
EE.
Automatic Primary Containment Isolation Valves - Are primary containment isolation valves which receive an automatic primary containment group isolation signal.
1 See FSAR Figure 1.6-1 i
Revision 50 Amendment No. 27, 773,128
<