ML20064B054
| ML20064B054 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/21/1990 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20064B053 | List: |
| References | |
| NUDOCS 9010040284 | |
| Download: ML20064B054 (3) | |
Text
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Technical Specif. cation change 1
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90 toc 40284-900921
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- 2.C;(6)
~.The licensee'shall fully implement and maintain in effect all' provisions'of,the Commission-approved physical security, grard' training and qualification, and safeguards contingency plans including amendments made pursuant to provisions-of the Miscellaneous Amendments and Search Requirements reviulons to 7
1 10 CFR 73.55'(51 FR 27817 and 27822) Land to the authority of 10' CFR 50.90 and 10 CFR 50.54(p).
The plano, which contain Safeguards ~Information protected under 10 CFR 73.21, are entitledsf " Oyster Creek Nuclear Generating Station Physical Security Plan," with revisions submitted through July 6, =1988:
"0yster Creek Nuclear Generating Station Training and Qualification Plan," with revisions submitted through June 24,.1986; and " Oyster Creak Nuclear Generating Station Mafeguards Contingency Plan," with revisions submitted.through J'ne 24,'1986.
Changes made in accordance with 10 CFR 73.55 shall:be implemented in accordance with the. schedule set'forth
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2.C.(7).
Inspections by a method acceptable to the NRC of all accessible i
. surfaces;and welds-of both core apray spargers and repair assemblies at.least once per 24 months will be performed so that.
meaningful comparisona of-any indications with previous
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inspections can be made.
Results of the inspections along with an evaluation 1of the safety significance of any new or j
m progressing indications will be provided to the commission's staff for review. Authorization will be obtained from the Commlusion's staff be fore the plant is reste- "ed from he refueling outage.
Should the staff determine-that new gracks,or further progression of existing cracks han occurred resulting in-3 unacceptable degradation of safety margins, the sparger will be replaced prior to' restart.
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The schedule given in the Attachments.to the commission's Order dated March 14, 1983, for the. completion'of NUREG-0737 Item III.D.3.4, control Room Habitability, is changed.to the-
. completion of (1) the interim system upgrade measures in Attachment I of the licensee's letter' dated June 4, 1985, by.the restart from-the Cycle 11 Refueling outage and (2) the final measures in Attachment II of'the same letter by the restart from.
the Cycle'12 Refueling outage.
'1 Amendment 127 Corrected l
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TABLE 4.15.2
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RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~
Channel ~
b c.
- ' Channel-
' Source
-Channel Functional. Surveillance'
~
Instrument.-
Check Check
. Calibration Test ~
. Required"
~
9 1.: Main condenser.'Offgas Treatment System D
'N.A.
Q M-c l Hydrogen Monitor,
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- 2. Main Stack Monitoring; System f
a.iRadioactive. Noble Gas Monitor (Low Range)
D M
1/24 Q*
b
- b. : Iodine.- Sampler.
W
.N.A.
N.A.
N.A.
b W
N.A.
N.A.
N.A.-
b
- c. Particulate Sample
('
- d. Effluent Flow Measuring D3vice D
N.A.
1/24 Q
'b e.. Sample Flow Measuring Device D
N.A.
R Q
b
- 3. Turoine Building Ventilation Monitoring L
System f
- a. Radioactive Noble Gas Monitor (Low.Rangei D
M 1/24 Q*
b b.
Iodine Sampler W
N.A.
N.A.
N.A.
b
- c. Particulate Sample W
N.A.
N.A.
N.A.
b
- d..
- uent Flow Measuring Device'.-
D N.A.
1/24 Q
b l
- e. I3stple Flow Measuring Device D
N.A.
R Q
b t
- 4. Offgas Building Exhaust' Ventilation.
- Monitoring _ System -
f
- a. Radioactive Noble Gas Monitor
.D
.M-R-
Q'-
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- b. Iodine Sampler W
N.A.
N.A.
'N.A.
b
- c. Particulate Sample W
N.A.
N.A.
N.A.
b
- d. Sample Flow Measuring. Device D
N.A.
R N.A.
b Leaend: S = once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; D = once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;.W = once per.7 days; M = once per.31 days; Q = once per'92 days; SA = once per 184 days; R = once per"18.mos; S/U = before each reactor startup;
.P = completed before.each release; N.A. = Not Applicable; 1/24-= once per 24 months.
. Amendment 127 Corrected.
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