ML20154L964

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Amend 2 to License NPF-36,revising Tech Specs to Reflect Conversion of One of Two Low Range Reactor Bldg Standby Vent Sys Noble Gas Radiation Monitors to Low Range Plant Vent Stack Noble Gas Radiation Monitor
ML20154L964
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 03/04/1986
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154L961 List:
References
NUDOCS 8603130206
Download: ML20154L964 (7)
v • d • e


Text

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M 88%q'o UNITED STATES 8 g NUCLEAR REGULATORY COMMISSION 3 WASHINGTON, D. C. 20555

%.....),t LONG ISLAND LIGHTING COMPANY DOCKET NO. 50-322 SHOREHAM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2 License No. NPF-36

1. The Nuclear Regulatory Comission (the Comission or the NRC) having found that:

A. The application for an amendment filed by the Long Island Lighting Company, dated October 21, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the pubile, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-36 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8603130206 960304 gDR ADOCK 05W J22

3. This amendment is effective upon issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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, ( L-Walte.r R. Butler, Director i BWR Project Directorate No. 4

Division of BWR Licensing -

Enclosure:

Changes to the Technical Specifications Date of Issuance: W 04 gp t

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ATTACHMENT TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO. NPF-36 DOCKET NO. 50-322 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT 3/4 3-71* 3/4 3-71 3/4 3-72 3/4 3-72 3/4 3-73* 3/4 3-73 3/4 3-74 3/4 3-74

  • These pages have not been revised by this amendment, but are included because the accompanying page on the other side of the sheet has been revised.

, INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CO'NDITION FOR OPERATION 3.3.7.5 The accident monitoring instrumentation channels shown in Table 3.3.7.5-1 shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

With one or more accident monitoring instrumentation channels inoperable, take the ACTION required by Table 3.3.7.5-1.

SURVEILLANCE REQUIREMENTS 4.3.7.5 Each of the above required accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.5-1.

( .

SH0REHAM - UNIT 1 3/4 3-71

1 TABLE 3.3.7.5-1 ACCIDENT IGNITORING INSTMBENTATION MINIMUM l REQUIRED NUfBER CHANNELS INSTMNENT OF CHAf00ELS OPERA 8LE ACTION E

Z 1. Reactor Vessel Pressure 2 1 80 w

2. Reactor Vessel Water Level 2 1 80
3. Suppression Pool Water Level 2 1 80
4. Suppression Pool Water Temperature 2/ sector 1/ sector 80
5. Drywell Pressure - ' ' 2 1 80
6. Drywell Air Temperature 1 1 80

$ 7. Dryuell and Suppression Chamber Oxygen Concentration 2 1 80 w

0 8. Drywell and Suppression Chamber Hydrogen Concentration Analyzer and Monitor 2 1 80

9. Safety / Relief Valve Position Indicators 1/ valve 1/ valve 80
10. Primary Containment Gross Radiation Monitors 2 1 81
11. High Range Plant Vent Stack
  • 1 1 81
12. High Range Reactor 81dg. Stane y Ventilation System
  • 1 1 81
13. Low Range Reactor Bldg. Staney Ventilation System
  • 1 1 81
14. Low Range Plant Vent Stack" 1 1 81 8 *Iloble gas monitors.

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2

TABLE 3.3.7.5-1 (Continued)

. ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 -

a. With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
b. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hour:.

ACTION 81 - With the nunber of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

a. Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and
b. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following ti.e event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

SHOREHAM - UNIT 1 3/4 3-73

TABLE 4.3.7.5-1 y ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g CHANNEL CHANNEL INSTRlRENT Cl!ECK CALIBRATION h 1. Reactor Vessel Pressure M R Q 2. Reactor Vessel Water Level M R

3. Suppression Pool Water Level M R
4. Suppression Pool Water Temperature M R
5. Drywell Pressure M R
6. Drywell Air Temperature M R
7. Drywell and Suppression Chamber Oxygen Concentration M R***
8. Drywell and Suppression Chamber Hydrogen Concentration Analyzer and Monitor M Q*

y 9. Safety / Relief Valve Position Indicators M R ,

10. Primary Containment Gross Radiation Monitors M R**

y

% 11. High Range Plant Vent Stack # M R

12. High Range Reactor Bldg. Standby Ventilation Systenf M R
13. Low Range Reactor Bldg. Standby Ventilation System # M R
14. Low Range Plant Vent Stack # M R

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  • Using calibration sample gas containing:
a. Zero volume percent hydrogen, balance nitrogen.

g b. Twenty nine volume percent hydrogen, balance nitrogen.

    • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector

$ for range decades above 10 R/hr and a one point calibratione check of the detector below 10 R/hr with an 4 installed or portable gamma source. -

      • Using calibration sample gas containing: -

m a) Zero volume percent oxygen, balance nitrogen b) Twenty-nine volume percent oxygen, balance nitrogen.

  1. Noble gas monitors.
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