ML18051B398

Application for Amend to License DPR-20,modifying Tech Specs Concerning Operability of Primary Coolant Sys Leakage Detection Sys Per NUREG-0820,Section 4.15.2, Integrated Plant Safety Assessment Rept. Fee Paid

ML18051B398
Person / Time
Site:	Palisades
Issue date:	05/23/1985
From:	Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
Shared Package
ML18051B399	List: ML18051B398 ML18051B400
References
RTR-NUREG-0820, RTR-NUREG-820 NUDOCS 8505290079
Download: ML18051B398 (5)

Text

consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 May 23, 1985 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST -LEAKAGE DETECTION SYSTEM David J VandeWalle Director of Nuclear Licensing 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 Primary Coolant System leakage detection systems in accordance with Integrated Plant Safety Assessment Report (IPSAR) section 4.15.2 (NUREG-0820, 10/82). This Change Request replaces the Change Request submitted December 13, 1983 in response to a number of questions posed by the NRC reviewers.

A check in the amount of $150.00 is enclosed as required by 10CFR170.21.

Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector

-Palisades Attachment PDR ADOCK 05000255 I I p. PDR . ) OC0585-0203A-NL04 CONSUMERS POWER COMPANY DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL 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. Changes: The following proposed Technical.

Specification changes address the operability requirements of installed Reactor Coolant System Leakage Detection Systems. Revised Technical Specifications pages are attached with the proposed changes identified by a vertical line in the right-hand margin. 1) Add a new sub-section 3.1.10 as follows: 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 above COLD SHUTDOWN.

The minimum number of operable channels for each system is specified in Table 3.17.4. 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 of 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 are 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 the gaseous containnient atmosphere monitoring system is INOPERABLE.

TS0884-0001A-LI01-NL04 2 c. If less than two systems of part (a) are OPERABLE, the reactor shall be placed in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Section 3.0.3 and 3.0.4 not applicable.

Basis Maintaining the primary coolant system leakage detection systems in accordance with section 3.1.10 above, assures that adequate leakage detection capability is available in addition to the daily primary coolant system inventory calculation.

References (1) Regulatory Guide 1.45 (2) NUREG-0820, October 1982 Section 4.15.2 (3) NRG Letter dated June 22, 1983 2) Add the following instruments to Table 3.17.4: 16. Containment Pressure (PT-1805A and PT-1812A)

17. Containment Sump Water Level (LT-0382 and LT-0383) 18. Containment Floor Water Level (LE-0446A and LE-0446B)

19. Gaseous Containment Monitoring System (RE-1817) (g) 1 1 1 1 20. Containment Humidity 3 Detectors (HT-1812, HT-1813, HT-1814, HT-1815) 21. Containment Air Cooler 3 Condensate Level Switches (LS-0817, LS-0865, LS-0868, LS-0870) None None None None None None Not Required Below 210°F Not Required Below 210°F Not Required Below 210°F Not Required Below 210°F Not Required Below 210°F Not Required Below 210°F (g) Three of the four supply valves (SV-1819, 1820, 1821, and 1822) to RE-1817 must be operable with their associated containment air cooler (A or B) in service. TS0884-0001A-LI01-NL04

3) Add the following instruments to Table 4.1.3, and renumber current items 15-18 to utilize the vacant item 14. 11. Containment Building Humidity Director b. Check s b. Comparison of Channels 18. Containment Pressure a. Check s a. Comparison of Wide Range Channels b. Calibrate R b. Known pressure applied to sensors 19. Containment Sump a. Check s a. Comparison of Water Level Instrument Channels b. Calibrate R b. Known differential pressure applied to sensors 20. Containment Floor a. Check s a. Comparison of Water Level Instrument Channels b. Calibrate R b. Known level applied to transducer

21. Containment Air Cooler a. Test R a. Move float and Condensate Level verify control Switches room alarm 22. Gaseous Containment

a. Check D a. Normal readings Monitor (RE 1817) observed and internal test signals used to verify instrument operation

b. Calibrate R b. Exposure to known external radiation source c. Test M c. Detector exposed to remote operated radiation check source II. Discussion:

The attached proposed Technical Specification Changes have been submitted to comply with the Integrated Plant Safety Assessment Report (IPSAR), Section 4.15. The proposed changes to Tables 3.17.4 and 4.1.3 regarding the containment pressure instruments, containment sump water level instruments and containment floor water level instruments which were previously proposed in June, 1982 appear again in this proposed change request in the interest of continuity and to completely address the Leakage Detection System topic in one submittal.

TS0884-0001A-LI01-NL04 3

4 III.

• Basis For Determination of No Significant Hazards Consideration We have reviewed the proposed change to the Palisades Technical Specifications being made to add operability requirements for the Primary Coolant System leak detection systems to determine whether or not this change involves a significant hazards consideration.

In our review, we have used the guidance of certain examples (48FR14870).

One of the examples (ii) in this guidance is if a change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications; it can be considered not likely to involve significant hazards considerations.

Since this proposal change adds requirements in accordance with Integrated Plant Safety Assessment Report (IPSAR), Section 4.15.2, we have determined that this change falls within the example and therefore the change does not involve a significant hazards consideration.

IV. 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 ,,Jli3 b 1.W fir R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me day of 1985, My commission SHERRY l YNN DURFEY Notary Public, Jackson County, Mich. My Commission Expirns Nov. 5, 1985 TS0884-0001A-LI01-NL04 c 5, 1986.