ML18051A752: Difference between revisions

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consumers
consumers Power
* Power
                             --cinnpany*-----          --- ----- -*---- -- ---- -----
                             --cinnpany*-----          --- ----- -*---- -- ---- -----
General_Offlces: 1945 West Parnell Road, Jackson, Ml 49201*1517) 71;18-0550 December 13, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - L~CENSE DPR          . PALISADES PLANT .:.. SEP TOPIC III-5.A "OPERABILITY OF LEAKAGE DETECTION SYSTEMS"
General_Offlces: 1945 West Parnell Road, Jackson, Ml 49201*1517) 71;18-0550 December 13, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - L~CENSE DPR          . PALISADES PLANT .:.. SEP TOPIC III-5.A "OPERABILITY OF LEAKAGE DETECTION SYSTEMS"

Latest revision as of 13:35, 3 February 2020

Application to Amend License DPR-20 Tech Specs Re SEP Topic III-5.A, Operability of Leakage Detection Sys, Per NUREG- 0820.Proposed Tech Spec Changes Made to Comply W/Integrated Plant Safety Assessment Rept (Ipsar) Section 4.15
ML18051A752
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/13/1983
From: Vandewalle D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML18051A753 List:
References
RTR-NUREG-0820, RTR-NUREG-820, TASK-03-05.A, TASK-3-5.A, TASK-RR NUDOCS 8312190101
Download: ML18051A752 (4)


Text

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consumers Power

--cinnpany*----- --- ----- -*---- -- ---- -----

General_Offlces: 1945 West Parnell Road, Jackson, Ml 49201*1517) 71;18-0550 December 13, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - L~CENSE DPR . PALISADES PLANT .:.. SEP TOPIC III-5.A "OPERABILITY OF LEAKAGE DETECTION SYSTEMS"

- REQUEST FOR CHANGE TO THE TECHNICAL SPECIFICATIONS Attached are three (3) originals and thirty-seven (37) conformed copies of a Request for Change to the Palisades Technical Specifications. The requested change incorporates the requirements to modify the Technical Specifications concerning the operability of the leakage detection systems in accordance with IPSAR section'4.15.2 (NUREG-0820, 10/82).

Since the subject of this change has been extensively reviewed under*

Systematic Evaluation Program topic III-5.A, this change is considered to be pro forma or administrative in nature. Therefore, a check in the amount of

$1,200.00 is attached pursuant to 10 CFR 170.22 (Class II).

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David J VandeWalle Nuclear Licensing Administrator CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachments 8312190101 831213

~ PDR ADOCK 05000255

'.:.. oo_P_ -- - - --- - - ___ PDR OC1083-0003A-NL02

CONSUMERS POWER COMPANY DOCKET 50-255 - LICENSE DPR PALISADES PLANT

--REQUEST FOR CHANGE TO TECHNlCAL--SPECIFICATIONS--

For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20,

_Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:

I. CHANGE(s)

A. Revise the Table of Contents - Appendix A to read as follows:

3.1.10 Leakage Detection System 3-25c B. Add the following sub-section to Sec_tion 3.1:

3.1.10 Leakage Detection Systems Specifications

a. The following primary coolant system leakage detection systems shall be OPERABLE, except as specified in part (b) below, whenever the reactor is in a HOT SHUTDOWN, HOT STANDBY; OR POWER OPERATION condition:
1. A containment atmosphere monitoring system detecting gaseous radioactivity.
2. A containment atmosphere monitoring system detecting
  • humidity.
3. A containment sump water level monitoring system.
4. A containment air cooler condensate flow system.
b. Operations may continue for a period up to 30 days provided:
1. At least two of the four systems of part (a) are OPERABLE, and
2. Grab samples of the containment atmosphere ate obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event that both of the containment atmosphere monitoring systems (gaseous and humidity) are INOPERABLE.
c. If less than two systems of part (a) are OPERABLE the reactor must be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ~nd in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

OC1083-0001A-NL02

2 Basis By maintaining the availability of the primary coolant system leakage detection systems in accordance with parts a, b, and c above, in addition to the daily primary coolant system leakage inventory calculation, adequate leakage detection is assured at all times. The leakage detection systems given in part a, of the above specifications, have a sensitivity sufficient to detect leakage that is within the requirements of Section 3.1.5 Primary Coolant System Leakage Limits.

I. CHANGES (Continued)

References (1). Regulatory Guide 1.45 (2) NUREG-0820, October 1982 Section 4.15.2 *

(3) NRC Letter dated June 22, 1983 C. Add the following to Table 4.1.3 of Section 4.1 Instrumentation and Control:*

25. Condensate Flow a. Test R a. Move Float and From Air Coolers Verify Control Room Alarm NOTE: Revised Technical Specification pages are ilttached. Proposed changes are shown by a vertical line in the right-hand margin. The items shown in brackets indicate previously proposed changes that have been

~ubmitted but not approved as of yet.

II. DISCUSSION The Proposed Technical Specification Changes have been submitted to comply with the Integrated Plant Safety Assessment Report (IPSAR) Section 4.15. The Proposed Technical Specifications address the concerns of the operability of installed Leakage Detection Systems. The Technical Specifications already incorporate the surveillance functions of the containment atmosphere gaseous radioactivity and humidity monitoring system, Table 4 .1. 3 Items 4 and 11 respectively.

A previously proposed Technical Specification added the surveillance of the sump water level monitor, Item 21 in the attached proposed Table 4.1.3.

OC1083-0001A-NL02

3 III. CONCLUSION The Palisades Plant Review Committee has reviewed this .Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.

CONSUMERS POWER COMPANY By R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 13th day of December, 1983.

ey, Notary ., ..

County, Michigan -.

My commission expires November 5, 1986.

SHERRY l YNN DURFEY .

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!1' publ"

  • 1c, Jackson County M" ~

re-:,, r- c:-***: *.* ; ,. * . '

  • II:. *

"'*; ., *.!,,;,.;1:,~icn .:..:(;~ii.\~:; N9v. 5, 1985 OC1083-0001A-NL02