ML17059B316

Errata to Amend 77 to License NPF-69.Provides Replacement Pages to Be Registered in TS

ML17059B316
Person / Time
Site:	Nine Mile Point
Issue date:	10/15/1996
From:	Hood D Office of Nuclear Reactor Regulation
To:	Sylvia B Niagara Mohawk Power Corp
Shared Package
ML17059B317	List: ML17059B316
References
NPF-69-A-077 NUDOCS 9610210033
Download: ML17059B316 (16)

Text

INDEX LIMITIN NDITI NS F R

PERATI N AND RVEILLAN E RE IREMENT REA TIVITY NTR L

Y TEM (Continued)

PA E

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM............................

3/4 1-19 Figure 3.1.5-1 Sodium Pentaborate Tank Volume vs. Concentration Requirements..

~ 3/4 1-22 4.2 P

WER DISTRIBUTION LIMIT 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.................

3/4 2-1 3/4.2.2 AVERAGE POWER RANGE MONITOR SETPOINTS.....................

3/4 2-2 3/4.2.3 MINIMUMCRITICALPOWER RATIO (ODYN OPTION B).................

3/4 2-3 3/4.2.4 LINEAR HEAT GENERATION RATE................ ~.......... ~.... 3/4 2-5 4.

IN TR MENTATI N 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION........ ~.....,.. 3/43-1 Table 3.3.1-1 Reactor Protection System Instrumentation...................

~. 3/4 3-2 Table 3.3.1-2 Deleted..............................................

3/4 3-6 Table 4.3.1.1-1 Reactor Protection System Instrumentation Surveillance Requirements... ~....... ~........................ ~.......... 3/43 7 3/4.3.2 ISOLATION ACTUATIONINSTRUMENTATION.......................

3/4 3-10 Table 3.3.2-1 Isolation Actuation Instrumentation.. ~................... ~...

3/4 3-12 Table 3.3.2-2 Isolation Actuation Instrumentation Setpoints............ ~......

3/4 3-17 Figure 3.3.2-1 AllowabIe and Trip Setpoint Values for the Main Steam Line Tunnel Lead Enclosure...

Table 3.3.2-3 Deleted

. ~......

3/4 3-19B 3/4 3-20 Table 3.3.2-4 Valve Groups and Associated Isolation Signals

. ~................

3/4 3-22 Table 4.3.2.1-1 Isolation Actuation Instrumentation Surveillance Requirements....

3/4 3-25 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION 3/4 3-29 Table 3.3.3-1 Emergency Core Cooling System Actuation Instrumentation........

3/4 3-30 Table 3.3.3-2 Emergency Core Cooling System Actuation Instrumentation etpolnts

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

S Table 3.3.3-3 Deleted 3/4 3-35 3/4 3-39 NINE MILE POINT - UNIT 2

'P6i02i0033 96i0i5 PDR ADQCK 050004i0 P

PDR v

Amendment No. 6, 6, 77

i

~

TABLE 3.3.2-2 zzlll Im U0z I

C hD 1.

Primer n ainmen I ola i n i nals (Continued) a.

Reactor Vessel Water Level*

1)

Low, Low, Low, Level 1

2)

Low, Low, Level 2 3)

Low, Level 3 TRIP SETPOINT a17.8 in.

~108.8 in.

a159.3 in.

ALLOWABLEVALUE

~10.8 in.

~101.8 in.

~157.8 in.

IS LATIONACTUATIONINSTRUIMIENTATIONSETPOINTS b.

Drywell Pressure

- High c.

Main Steam Line a1.68 psig x1.88 psig 60 C

4) 1)

Radiation - High**

2)

Pressure - Low 3)

Flow - High d.

Main Steam Line Tunnel a3x Full Power Background

<3.6x Full Power Background a766 psig a746 psig x121.5 psid

<122.8 psid 1)

Temperature - High 2) hTemperature

- High 3)

Temperature

- High MSL Lead Enclosure***

e.

Condenser Vacuum Low f.

RHR Equipment Area Temperature

- High (HXs/ARB Pump Rooms) 167.2oF

<70 O'

<148.2'F a8.5 in Hg vacuum 135oF 170 6oF 71 7oF

~151.6'F a7.6 in. Hg vacuum 144 5oF z0 lSbk.

h.

SGTS Exhaust - High Radiation K5.7X1 0 pCI/CC g.

Reactor Vessel Pressure

- High (RHR Cut-in 5128 psig Permissive) c148 psig c1.0x10 2 pCi/cc

DATED: October 15 1996 CORRECTION FOR AMENDMENT NO. 77, NINE MILE POINT NUCLEAR STATION, UNIT 2 Docket File PUBLIC PDI-1 Reading S. Varga, 14/E/4 S.

Bajwa S. Little D.

Hood OGC G. Hill (2), T-5 C3 C. Grimes, ll/E/22 ACRS L. Doerf1 ein, Regi on I cc:

Plant Service list

Mr. B.

Ral ph Syl vi a Executive Vice President Generation Business Group and Chief Nuclear Officer Niagara Mohawk Power Corporation Nuclear Learning Center 450 Lake Road

Oswego, NY 13126

SUBJECT:

CORRECTIONS FOR AMENDMENT NO. 77, NINE MILE POINT NUCLEAR STATION, UNIT 2 (TAC NO. H95405)

Dear Hr. Sylvia:

On September 17, 1996, the Commission issued Amendment No.

77 to Facility Operating License No.

NPF-69 for the Nine Mile Point Nuclear Station, Unit 2.

The amendment revised Technical Specification 3/4.3.2, "Isolation Actuation Instrumentation," to establish a range of allowable values and trip setpoints for high temperatures in the Main Steam Line Tunnel Lead Enclosure.

Amendment No.

77 provided replacement pages to be inserted in the Technical Specification.

Please replace pages v and 3/4 3-17 provided to you September 17, 1996, with the enclosed copies.

The enclosed copies correctly identify the superceded amendment numbers.

This editorial correction does not affect our previous findings and is in accordance with my recent discussion with Mr. T. Zallnick of your organization.

Sincerely, Docket No. 50-410

Enclosures:

Pages v and 3/4 3-17 cc w/encls:

See next page Darl S.

Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nucle'ar Reactor Regulation DOCUMENT NAME':II,NHP2iCORRECTION.77 To receive a copy of this document, indicate in the box:

"C" - Copy, without attachment enclosure "E" - Co with attachment enclosure "N" - No co y OFFICE PH:PDI-1 E

LA:PDI-1 D:

I-1 DATE 1D/ 5/96 1D/ I

/96 1

/96 0

Icosa Recor Copy NAHE DHood:rsl 3>5 SLittle J

/96

gPS REGS (4

0 Cy 0p r

0 <

>r p

a

+~

~O

~>>*<<~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205!I5-0001 October 15, 1996 Hr. B. Ralph Sylvia Executive Vice President Generation Business Group and Chief Nuclear Officer Niagara Hohawk Power Corporation Nuclear Learning Center 450 Lake Road

Oswego, NY 13126

SUBJECT:

CORRECTIONS FOR AHENDHENT NO. 77, NINE HILE POINT NUCLEAR STATION, UNIT 2 (TAC NO. H95405)

Dear Hr. Sylvia:

On September 17, 1996, the Commission issued Amendment No.

77 to Facility Operating License No. NPF-69 for the Nine Hile Point Nuclear Station, Unit 2.

The amendment revised Technical Specification 3/4.3.2, "Isolation Actuation Instrumentation," to establish a range of allowable values and tr'ip setpoints for high temperatures in the Hain Steam Line Tunnel Lead Enclosure.

Amendment No.

77 provided replacement pages to be inserted in the Technical Specification.'lease replace pages v and 3/4 3-17 provided to you September 17, 1996, with the enclosed copies.

The enclosed copies correctly identify the superceded amendment numbers.

This editorial correction does not affect our previous findings and is in accordance with my recent discussion with Hr. T. Zallnick of your organization.

Sincerely, Docket No. 50-410

Enclosures:

Pages v and 3/4 3-17 cc w/encls:

See next page 8wil Darl S.

Hood, Senior Project Hanager Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

t~

B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit 2 CC:

Mr. Richard B. Abbott Vice President and General Manager Nuclear Niagara Hohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Mr. Martin J. HcCormick, Jr.

Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hs.

Deni se J. Wolniak Manager Licensing Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hr. Kim A. Dahlberg General Hanager Projects Niagara Mohawk Power Corporation Nine Hile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Mr. John T. Conway Plant Manager, Unit 2 Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P.O.

Box 63

Lycoming, NY 13093 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector Nine Mile Point Nuclear Station P.O.

Box 126 Lycomin'g, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Hr. Richard H. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue

Albany, NY 12210 Mark J. Wetterhahn, Esquire Winston

& Strawn 1400 L Street, NW.

Washington, DC 20005-3502 Gary D. Wilson, Esquire Niagara Hohawk Power Corporation 300 Erie Boulevard West

Syracuse, NY 13202 Hr. F. William Valentino, President New York State

Energy, Research, and Development Authority 2 Rockefeller Plaza

Albany, NY 12223-1253 Supervisor Town of Scriba Route 8, Box 382

Oswego, NY 13126 Mr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus

Syracuse, NY 12223 Hr. John V. Vinquist, HATS Inc.

P.O.

Box 63

Lycoming, NY 13093

INDEX LIMITIN NDITI N F

R PERATI N AND VEILLAN E RE IREMENT REA TIVITY ONTR L

Y TEM (Continued) 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM............................

3/4 1-19 Figure 3.1,5-1 Sodium Pentaborate Tank Volume vs. Concentration Requirements...

3/4 1-22 4.2 POWER DI TRIBUTI N LIMIT 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.................

3/4 2-1 3/4.2.2 AVERAGE POWER RANGE MONITOR SETPOINTS.....................

3/4 2-2 3/4.2.3 MINIMUMCRITICALPOWER RATIO (ODYN OPTION B).................

3/4 2-3 3/4.2A LINEAR HEAT GENERATIONRATE...........................

3/4 2-5 4.

IN TR MENTATI 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................

~ 3/4 3-1 Table 3.3.1-1 Reactor Protection System Instrumentation............. ~....... 3/4 3-2 Table 3.3.1-2 Deleted..............................................

3/4 3-6 Table 4.3.1

~ 1-1 Reactor Protection System Instrumentation Surveillance Requirements.. ~........................ ~...................

3/4 3 7 3/4.3.2 ISOLATION ACTUATIONINSTRUMENTATION.......................

3/4 3-10 Table 3.3.2-1 Isolation Actuation Instrumentation.. ~.......................

3/4 3-12 Table 3.3.2-2 Isolation Actuation Instrumentation Setpoints... ~....

~

~

~

~

~

~

~

~

~

~

~ 3/4 3-17 Figure 3.3.2-1 Allowable and Trip Setpoint Values for the Main Steam Line Tunnel Lead Enclosure...................................

3/4 3-198 Table 3.3.2-3 Deleted...............

~.

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ 3/4 3-20 Table 3.3.2-4 Valve Groups and Associated Isolation Signals..................

3/4 3-22 Table 4.3.2.1-1 Isolation Actuation Instrumentation Surveillance Requirements....

3/4 3-25 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION 3/4 3-29 Table 3.3.3-1 Emergency Core Cooling System Actuation Instrumentation........

3/4 3-30 Table 3.3.3-2 Emergency Core Cooling System Actuation Instrumentation etp 0 Illts

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

S Table 3.3.3 3 Deleted 3/4 3-35 3/4 3-39 NINE MILE POINT - UNIT 2 v

Amendment No. 6, 6, 77

4

~

zzm g

Im 00z I

Cz h)

TRIP FUNCTION 1.

Primer on ainmen Isola ion i nal (Continued) a.

Reactor Vessel Water Level*

1)

Low, Low, Low, Level 1

2)

Low, Low, Level 2 3)

Low, Level 3 TRIP SETPOINT a17.8 in.

a 108.8 in.

R159.3 in.

ALLOWABLEVALUE

~10.8 in.

~101.8 in.

R 157.8 in.

TABLE 3.3.2-2 ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTS

~ g CD 4

CD b.

Drywell Pressure

- High c.

Main Steam Line 1)

Radiation - High**

2)

Pressure

- Low 3)

Flow - High d.

Main Steam Line Tunnel 1)

Temperature

- High 2) hTemperature - High 3)

Temperature

- High MSL Lead Enclosure***

e.

Condenser Vacuum Low f.

RHR Equipment Area Temperature

- High (HXs/ARB Pump Rooms) a1.68 psig

<3x Full Power Background

>766 psig

<121.5 psid 167.2oF

<70.0'F a 148.2'F a8.5 in Kg vacuum 135oF c1.88 psig a3.6x Full Power Background a 746 psig s122.8 psid

~170.6'F 71 7oF 151.6oF a7.6 in. Hg vacuum 144.5oF z0 CD V

h.

SGTS Exhaust - High Radiation

~5.7x10 yCi/cc g.

Reactor Vessel Pressure - High (RHR Cut-in

@128 psig Permissive) c148 psig s1.0x10 yCi/cc