ML20209E200

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Proposed Change to Tech Spec 5-15,incorporating Provision for Preparation of Special Repts in Event of Inoperable Channels of post-accident Monitoring Instrumentation.Related Info Encl
ML20209E200
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/15/1987
From:
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20209D101 List:
References
TAC-62069, NUDOCS 8704290452
Download: ML20209E200 (2)


Text

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- ATTACHMENT A 5.9.3 Special Reports Special reports shall be submitted to the Regional Administrator of j the appropriate NRC Regional Office within the time period specified //

for each report. These reports shall be submitted covering the A activities identified below pursuant to the requirements of the applicable reference specification where appropriate:

a. In-service inspection report, reference 3.3.
b. Tendon surveillance, reference 3.5
c. Containment structural tests , reference 3.5
d. Special maintenance reports.
e. Containment leak rate tests , reference 3 5
f. Radioactive effluent releases , reference 2.9
g. Materials radiation surteillance specimens reports , reference 3.3.
h. Fuel performance following each refueling outage,
i. Fire protection equipment outage , referenge 2.19.'

. Fbst-ac.ciclent ManifoRing Instrurvientadiotz, t ele.rence. 2.2) 59.4 nique Reporting Requirements

a. Radioactive Effluent Release Report A report covering the operation of the Fort Calhoun Station during g the previous six months shall be submitted within 60 days after //

Januarf 1 and July 1 of each year.

The radioactive effluent release report shall include a summar/ of the quantities of radioactive liquid and gaseous effluents and solid vaste released from the plant as outlined in Regulatory Guide 1.21, Revision 1.

The radioactive effluent release report shall include a summary of the meteorological conditions concurrent with the release of

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  1. I gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1.

The radioact,1ve effluent release report shall include an assessment l of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in f Regulator / Guide 1.21, Revision 1. In addition, the unrestricted // )

area boundarf maximum noble gas gamma air and beta air doses shall #

be evaluated. The meteorological conditions concurrent with the l 5-15 Amendment No. 9,24,38,)(6,h 670r,2?O452 870415 i PDR ADOCKOSOOg5 P

l I

ATTACHMENT B No Significant Hazards Considerations This change will not increase the probability of any accident previously analyzed. The change adds the requirement to submit the Post-accident Monitoring Instrumentation Special Report referenced in Section 2. of the Technical Specifications.

This change will not create the possibility of a new or different accident than any previously analyzed. The change does not create a change in the method of operation. Only the administrative requirements to submit special reports is addressed to make sections of the Technical Specifications consistent.

The change will not reduce the margin of safety as defined in the basis of any Technical Specification. The change does not affect any mode of operation and only serves to clarify reporting requirements applicable to the Technical Specification.

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