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Amend 7 to License NPF-36,changing Footnote of Surveillance Requirement 4.4.3.1.c on RCS Leakage Detection Sys & Tech Spec Section 3.3.7.9 on Fire Detection Instrumentation
	ML20237G460
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	08/14/1987
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
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ML20237G440	List: ML20237G437; ML20237G460; ML20237G470;
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	NUDOCS 8708240093
	Download: ML20237G460 (11)
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f LONG ISLAND LIGHTING COMPANY ,

DOCKET NO. 50-322 SHOREHAM NUCLEAR PCWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. NPF-36

1. The Nuclear Regulatory Commission (the Commission) has found that A. The application for amendment by Long Island Lighting Company (the licensee), dated November 16 and December 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as s amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted I

in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or tn 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 l as indicated in the attechment to this license amendment, and paragraph 2.C.(2) <

of Facility Operating License No. NPF-36 is hereby amended to read as follows:

Technical Specifications

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 7 are hereby incorporated into this license.

Long Island Lighting Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8708240093 070814 DR ADOCK 0500 2

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3. This license amendment is effective as of its date of issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION j l

/s/

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

j Changes to the Technical Specifications Date of Issuance: August 14, 1987 l

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3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION I /

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: August 14, 1987

ATTACHMENT TO LICENSE AMENDMENT NO. 7

. FACILITY OPERATING LICENSE NO. NPF-36 DOCKET NO. 50-322 i

Replace the following pages. of the' Appendix "A" Technical Specifications with '

the attached pages. The revised pages are identified by Amendment number and i contain vertical lines indicating the area of change. Overleaf pages provided i to maintain document completeness.*

Remove Insert 3/4 3-81 3/4 3-81 3/4 3-81a 3/4 3-82 3/4 3-82 3/4 3-83 3/4 3-83 3/4 3-84* 3/4 3-84*

3/4 4-9 3/4 4-9 3/4 4-10*. 3/4 4-10*

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4 INSTRUMENTATION i

FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3

3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3.7.9-1 shell be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

a.

With the number of OPERABLE fire detection instruments in one or

, 4 more zones:

1. Less than, but more than one-half of, the Total Number of c

Instruments shown in Table 3.3.7.9-1 for Function A, restore the inoperable Function A instrument (s) to OPERABLE status within 14 days or within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instruments (s) at least once per hour, unless the instrument (s) is located in an (Note 1) inaccessible zone, then inspect that inaccessible zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the air temperature at least once per hour at the locations listed in Specification 4.6.1.7 or Specification 4.7.9.

2. One less than the Total Number of Instruments shown in Table 3.3.7.9-1 for Function B, or one-half or less of the Total' Number of Instruments shown in Table 3.3.7.9-1 for Function A, or with any two or more adjacent instruments inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instruments (s) at least once per hour, unless the instrument (s) is located in an (Note 1) inaccessible zone, then inspect that inacces-sible zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the air tem-perature at least once per hour at the locations listed in Specification 4.6.1.7. or Specification 7.9.

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b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.9.1 Eachoftheaboverequiredrestorabletypefiredetectioninstrumentsl which are accessible during unit operation shall be demonstrated OPERABLE at

. least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire

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detectors which are not accessible due to specific unit operating conditions Note 1: zone may be declared to be inaccessible during specific operating conditions (e.g. containment during unit operation, HPCI/RCIC during system testing, main steam tunnel during unit operation).

i SHOREHAM - UNIT 1 3/4 3-81 Amendment No. 7 i

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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or when the specific detector becomes accessible, unless performed in the previous 6 months.

4.3.7.9.2 The supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.7.9.3 For nonrestorable spot-type detectors, after the fifteenth year at least two detectors out of every hundred, or fraction thereof, shall be removed every five years and sent to a testing laboratory for tests. The detectors that have been removed shall be replaced with new detectors. If a failure occurs on any of the detectors removed, additional detectors :,aall be removed and tested as a futher check on the installation until there is proven to exist either a general problem involving faulty detectors or a localized problem in-volving only one or two defective detectors.

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SHOREHAM - UNIT 1 3/4 3-81a Amendment No. 7

TABLE 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION SAFETY-RELATED ZONE TOTAL NUMBER OF INSTRUMENTS

HEAT SM0KE FLAME (x/y) (x/y) (x/y)

1. Control Building Emergency Switchgear Room 101 0/6 6/0 Emergency Switchgear Room 102 0/6 6/0 Emergency Switchgear Room 103

=,

0/6 6/0 )

Battery Room A 0/2 3/0 Battery Room B 0/2 4/0

, Battery Room C 0/3 5/0 Diesel Generator Room 101 0/9 1/0## 3/0 Diesel Generator Room 102 0/11 1/0## 3/0 (

'.i Diesel Generator Room 103 0/10 1/0## 3/0 i

>; Relay Room 0/24 14/0 {

HVAC Equipment Room El. 44'-0" 3/0 I HVAC Equipment Room El. 63'-0" 5/0 )

Chiller Equipment Room El. 44'-0". 10/0 l Chiller Equipment Room El. 63'-0" 10/0 }

CRAC - FLT 2A El. 63'-0" 4/0

, CRAC - FLT 2B El. 63'-0" 4/0 CRAC CR Exh El. 63'-0" 1/0 Corridor 8 E1. 25'-0" 5/0 a

Corridor 9 E1. 25'-0" 3/0 ,

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2. Reactor Building l

l Primary Containment # 4/0 l Secondary Containment El. 8'-0" 30/0 l Secondary Containment El. 40'-0" 38/0 l Secondary Containment El. 63'-0" 14/0 l Secondary Containment El. 78'-7" El. 95'-3", & 101'-6" 4/0 42/0 Main Steam Tunnel E1. 76'-5" 11/0** I Secondary Containment El. 112'-9" 2/0 55/0 Secondary Containment E1. 126'-9" 7/0

>' Secondary Containment

E1. 150'-9" & 1598-9" 5/0 27/0

, Secondary Containment E1. 175'-9" 3/0##

9 h MG Room 111 E1. 150'-9" 4/0 MG Room 112 El. 150'-9" 3/0

. MG Room 113A El. 161'-0" 4/0 r

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fc SHOREHAM - UNIT 1 3/4 3-82 Amendment No. 7

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P TABLE 3.3.7.9-1 (Continued) l FIRE DETECTION INSTRUMENTATION SAFETY-RELATED ZONE TOTAL NUMBER OF INSTRUMENTS

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-HEAT SM0KE FLAME kj 1

(x/y) (x/y) (x/y)

'1 MG Room 113B El. 161'-0"

! 3/0 MCC West Room El.~112'-9" 3/0 MCC East Room El. 112'-9" 2/0 Remote Shutdown Panel-Enclosure El. 63'-0" 0/2 HPCI Turbine El. 8'-0" 0/6 RCIC Turbine El. 8'-0"

- 0/5 1TK607R Horizontal Cable Trays 2/0 1TX600R Vertical Cable Trays 5/0 RBSVS - FLT - 1A El. 112'-9" 2/0 RBSVS - FLT - IB El. 112'-9" 2/0 MCC Room E1. 40'-0" 2/0 a

', 3. Turbine Building Electrical Manhole No. 1 El. 5'-8'" 0/2 2/0 l

(located in normal switchgear room) q 4. Screenwell Pump House d '-

Pump Cubicle A 3/0##

Pump Cubicle B 3/0##

M.

, 4 5. Yard s

Emergency Diesel F.O. Transfer Pump

House A 2/0 i

Emergency Diesel F.0. Transfer Pump 1" House B 2/0 Emergency Diesel F.0. Transfer Pump House C 2/0

TABLE NOTATIONS

(x/y): xisnumberofFunctionA(earlywarningareafirddetectionandnoti-fication) instruments. y is number of Function B (actuation of fire suppres-l4 sion system and notification) instruments.

'y #The fire detection instruments located within the primary containment are not i required to be OPERABLE during the performance of Type A Containment Leakage

".; , Rate Tests.

] ** Heat detectors are non restorable spot type fixed temperture, f,-

1. Includes projected beam type smoke detector SHOREHAM - UNIT 1 3/4 3-83 Amendment No. 7 a -

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INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION

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3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels ;

shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints l Set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The !

alarm / trip setpoints of these. channels shall be determined in accordance with l the Offsite Dose Calculation '4anual (ODCM).

l APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel l alarm / trip setpoint less conservative than required by the above -

specification, immediately suspend the release of radioactive liquid I effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid ef fluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.3.7.10.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.

4.3.7.10.2 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at least one circulating water pump shall be determined to be operating and providing dilution to the discharge structure whenever dilution is required to meet the site radioactive effluent

concentration limits of Specification 3.11.1.1.

SHOREHAM - UNIT 1 3/4 3-84 a

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y. RE CTOR COOLANT SYSTEM 7> 3/4.4 3 REACTOR COOLANT SYSTEM LEAKAGE

LEAKAGE DETECTION SYSTEMS

!, - LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

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a. The primary containment atmosphere particulate radioactivity monitoring system,

b. The primary containment sump flow monitoring system, and

c. Either the primary containment air coolers condensate flow indication system or the primary containment atmosphere gaseous radioactivity monitoring system.

APPLICABILITY: OPERATIONAL _ CONDITIONS 1, 2, and 3.

1 g ACTION:

J With only two of the above required leakage detection systems OPERABLE, N: operation may continue for up to 30 days provided grab samples of the contain -

,, ment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the h,

required gaseous and/or particulate radioactive monitoring system is inoperable; otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

[ SURVEILLANCE REQUIREMENTS i

4.4.3.1 The reactor coolant system leakage detection systems shall be

., demonstrated OPERABLE by:

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a. Primary containment atmosphere particulate and gaseous monitoring

.} systems performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a f

, CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL 1

, CALIBRATION at least once per 18 months.

b. Primary containment sump flow monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL '

CALIBRATION TEST at least once per 18 months.

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c. Primary containment air coolers condensate finw indication ii - system performance of a CHANNEL FUNCTIONAL TEST

at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months. j

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u *Not required if containment is closed.

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SHOREHAM - UNIT 1 3/4 4-9 Amendment No. 7 a

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l REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE.

b. S gpm UNIDENTIFIED LEAKAGE.

c. 25 gpm total leakage averaged over any 24-hour period.

d. 1 gpm leakage at a reactor coolant system pressure of 1000 + 40,

-120 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.

e. 2 gpm increase in UNIDENTIFIED LEAKAGE within any 4-hour period.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. With any reactor coolant system leakage greater than the limits in b.

and/or c., above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual or deactivated automatic valve, or check valve,* or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 4-hour period, identify the source of leakage increase as not service sensitive Type 304 or 316 austenitic stainless steel within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ;

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Which has been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.

SHOREHAM - UNIT 1 3/4 4-10 .

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ML20237G460

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