ML19030A956

Letter Request for Amendment No. 2 to Facility Operating License to Correct Typographical Error

ML19030A956
Person / Time
Site:	Salem
Issue date:	09/20/1976
From:	Librizzi F Public Service Electric & Gas Co
To:	Kniel K Office of Nuclear Reactor Regulation
References
Download: ML19030A956 (9)

Text

Public Service Electric and Gas Company 80 Park Place Newark, N September 2 0, Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Mr. Karl Kniel, Chief Light Water Reactors Branch No. 2 Gentlemen:

REQUEST FOR AMENDMENT 2 FACILITY OPERATING LICENSE DPR-70 NO. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 Mail Sec:tiOn llackei Cieri:

File Cy,,":!

In accordance with the Atomic Energy Act of 1954;- as ~mended, and the Regulations thereunder, we hereby transmit copies of the Request for Amendment 2 to Facility Operating License DPR-70 for Salem Nuclear Generating Station, No. 1 Unit.

This Request for Amendment 2 is required in order to correct typographical errors and to resolve conflicting operating re-quirements set forth in Appendix "A", Technical Specifications, which involve the containment atmosphere radiation monitoring equipment.

This submittal includes three (3) signed affidavits and 40 copies of the Request for ~..mendment 2.

The Energy People Very truly yours,

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Frank P. Libri~

General Manager -

Electric Production 95-2001 300M 8-75

U.S. NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-272 PUBLIC SERVICE ELECTRIC AND GAS COMPANY REQUEST FOR AMENDMENT 2 FACILITY OPERATING LICENSE NO. DPR-70 NO. 1 UNIT SALEM NUCLEAR GENERATING STATION Public Service Electric and Gas Company hereby submits Request for Amendment 2 to Facility Operating License No.

DPR-70 for Salem Nuclear Generating Station, Unit No. 1.

This amendment request pertains specifically to the contain-ment atmosphere radiation monitoring equipment.

The change is required in order to correct typographical errors and to resolve conflicting operating requirements set forth in Appendix A, Technical Specifications.

Respectfully submitted, PUBLIC SERVICE ELECTRIC AND GAS COMPANY By~

Frederick W. Schneider

STATE OF NEW JERSEY SS. :

COUNTY OF ESSEX FREDERICK W. SCHNEIDER, being duly sworn according to law, deposes and says:

I am a Vice President of Public Service Electric and Gas Company, and as such I signed Request for Amendment 2 to FACILITY OPERATING LICENSE NO. DPR-70.

The matters set forth in said Request for Amendment 2 are true to the best of my knowledge, information and belief.

Subscribed and before me this of 4-~..-8-vi...,

sworn to

,;:l D 'ft.. day

'.i.1:1..f I

Notary Public of New Jersey My Commission expires on

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REQUEST FOR AMENDMENT 2 FACILITY OPERATING LICENSE DRP-70 NO. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 In accordance with the Atomic Energy Act of 1954, as amended, and the regulations thereunder, PSE&G hereby requests that Facility Operating License DPR-70 for Salem Nuclear Generating Station, Unit No. 1, be amended as set forth below:

APPENDIX A, TECHNICAL SPECIFICATIONS

1.

Engineered Safety Feature Actuation System Instrumentation,

• Specification 3.3.2.1

a.

Table 3.3-3 (page 3/4 3-18), Item 3.C.2, Containment Atomosphere Radioactivity -*High: "TOTAL NUMBER OF CHANNELS" column should be changed from "4" to "3".

This is a typographical error, in that there are only three channels performing the required function instead of four.

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"MINIMUM CHANNELS OPERABLE" column khould be changed from "2" to "2**" and a footnote added as follows:

"**All three (3) channels may be removed from service and used for monitoring plant stack effluent rather than for monitoring containruent atmosphere for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

2 -

DOCKET NO. 50-272 per 24-hour interval while either purging the containment atmosphere or v~nting a gas decay tank."

A similar footnote exists in Specification 3.3.3.1, Radiation Monitoring Instrumentation, which allows for purging the containment atmosphere and venting a gas decay tank during normal plaht operation.

This change is necessary to maintain consistency between these specifications and to permit these operations to be accomplished.

Monitoring the plant stack is required by Appendix B, Environmental Technical Specifications 2.3.4.a and 2.3.4.b.

b.

Table 3.3-4 (page 3/4 3-25), Item 3.C.2, Containment Atmosphere Radioactivity:

A new item "3.C.2.c" should be added to include the fixed filter iodine monitor, with setpoints of "J;;. x background in the "TRIP SETPOINT" and "ALLOWABLE VALUES" columns.

This monitoring channel should be added since it also per-forms an automatic containment purge isolation function.

Incorporation of this item will maintain consistency with Specification 3. 3. 3.. 1, Radiation Mani taring Instrumentation.

2.

RADIATION MONITORING INSTRUME:~nATION, Specification 3. 3. 3. 1 Table 3.3-6 (page 3/4 3-36), Item 2.a.3, Fixed Filter Iodine -

3 -

DOCKET NO. 50-272 Purge and Pressure.- Vacuum Relief Isolation:

"MINIMUM CHANNELS OPERABLE" column should be changed from II 1 II to II 1 # II

• This is an apparent typographical error, since this monitor is an integral part of the other (gaseous and particulate) containment monitors and the associated footnote applies.

Incorporation of these changes in the Technical Specifications does not involve any system modifications, but serves only to permit smooth and proper operation of the affected systems.

These systems have been determined previously to be acceptable by the Regulatory staff.

The proposed changes do not alter any previous safety analyses and therefore, the health and safety of the public will not be endangered by their implementation.

The applicable pages with the proposed changes incorporated are attached.

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ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

.. ::* =~*. ~

MINIMUM TOTAL NO.

CHANNELS CHANNELS FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE

b.

Phase 118 11 Isolation

1)

Manual 2 sets of 2 1 set of 2 2 sets of 2

2)

Automatic

• 2 1

2 Actuation Logic

3)

Containment 4

2 3

Pressure--High-High

.. c.

Purge and Exhaust.

Isolation

1)

Manual 2

J 2

2 **

2)

Containment Atmo-3 1

sphere Radioactivity-High

4.

STEAM LINE ISOLATION

a.

Manual 1 /steam line 1/steam line 1/operating *.

steam 1 ine * * *

b.

Automatic 2

l 2

Actuation Logic

c.

Containment Pressure--

4 2

3 High-High

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. *1 APPLICABLE MODES

.. ACTION 1, 2~ 3, 4 18 e 1, *2, 3. 4 13 1, 2. 3 16 1,2,3,4 17 1, 2 *. 3. 4 17.. I

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1, 2, 3

.1s 1, 2. 3 13 1, 2. 3

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• All three (3) channels may be removed from service and used for monitoring plant stack effluent rather than for monitoring containment atmosphere for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval while either purging the containment atmospher~ or venting a gas decay tank.

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ENGINEE'RED SAFETY FEATURE ACTUATIOH SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT-** *

2.

Containment Atmosphere Radioactivity a)

Particulate b)

Gaseous c)

Iodine

4.

STEAM Lif{E ISOLATION

a.

Manual

b.

Automatic Actuation Logic

c.

Con ta inm'ent Pressure--Hf gh-Hi gh

d.

Steam F1ow*"fn Two Steam Lines--

. High Coincident with Tavn --Low-Low or Steam Line Pressure--~ow TRIP SETPOlNT

-~ 2 x background

~ 2 x background

~ 2 x background ALLOWABLE VALUES

~2 x background *

< 2 x background

~ 2 x background

' I l *.

Not Applicable Not Applicable

~ 23.5 psig

< A function defined as

'follows: A ~P corresponding to 40% of full steam flow between 0%.and 20% load*

and then a 6p increasing linearly to a ~P correspond-ing to 110% of full steam flow at full load Tavg ~ 543°F

> 500 psig steam line pressure Not Applicable Not A'pp11cab1e

< 24 psig

< A function defined as

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fol tows: A 6p* correspondin~*

to 44% of full steam flow.

• beb1ecn OX and 20% load and then a Ap increasing linearly to a 6p corresponding to lll.5X of full steam flow at full load Tavg ~ 541°F

~ 480 psig steam line pressure *

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-f TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM INSTRUMENT

• CHANNELS OPE RAil LE 1 I AREA MONITORS

a. Fuel Storage Pool'Area 1

2.

PROCESS MONITORS *

a. Containment *

1)

Gaseous Activity

• *111 a) Purge & Pressure-Vacuum Relief Isolation b)

RCS Leakage Detection

2) Air Particulate Activity 1#

a)

Purge & Pressure-Vacuum Relief Isolation b)

RCS Leakage * *.

Detection Fixed Filter Iodine-Purge & Pressure -

Vacuum Relief Isolation l#

I APPLICABLE MOO ES 1, 2, 3, 4 & 6 1, 2, 3 & 4

1. 2, 3, 4 & 6 1, 2, 3 & 4 1, 2, 3, 4 & 6 ALARM/TRIP

.SETPOHIT

~ 15 mR/hr

!. 2 x background N/A MEASUREMENT RANGE 10*1 - 104 mR/hr*

~

1 O 1* - 1 06 cpm

• 101 *- 106 cpm

~ 2 x background*

101 -* 106 cpm

• N/A 101 - 106 cpm

!,2-x background* 101 - 106 cpm

• With fuel in the storage pool or buildin~.

1. Channel may be removed from service and used for monitoring plant stack effluent rather than for monitoring containment atmosphere for up to 8.hours per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ipterval while either purging.<*:.

the containment atmosphere or venting a gas decay tank.

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