Text

Amend 8 to License NPF-14,changing Tech Specs to Correct Typographical Errors
	ML17139B355
Person / Time
Site:	Susquehanna
Issue date:	02/07/1983
From:	Schwencer A; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17139B356	List: ML17139B355; ML17139B357; ML17139B358;
References
	NUDOCS 8302180029
	Download: ML17139B355 (11)
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PENNSYLVAN!A PONER 8I LIGHT COHPANY N

SUSQUEHANNA STENh E

C R

C ATION, UNIT 1 Amendment No. 8 License Ho. NPF-14 1.

The Nuclear Regulatory Comoission (the Commission or the NRC) having found that:

A.

The application for an amendment filed by the Pennsylvania Power 8 Light Company dated October 22, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; C.

There is reasonable assurance:

(i) 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 in compliance IIIith the Commission's regulations; 0.

The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.

OBQ GIO OO rux 'i OQ GlQ Cil 'IX C)A CIILO 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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 8

, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.

PP8L shall operate the facility in accordance witIl the Technical Specifications and the Environmental Protection Plan.

OFFICE/

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This amendment is effective as of the date of issuance.

FOR TH HUCLE R REGULATORY COMt1ISSION A. Schwencer, Chief Licensing Branch Ho. 2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

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ATTACHMENT TO LICENSE AMENDMENT NO. 8 DOC ET NO.

1 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 3/4 6-3 3/4 6-4 3/4 8-17 3/4 8-18 3/4 11-17 3/4 11-18 INSERT 3/4 6-3 3/4 6-4 3/4 8-17 3/4 8-18 3/4 11-17 3/4 11-18

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION Continued ACTION (Continued) restore:

a.

The overall integrated leakage rate to less than or equal to 0.75 L, and b.

The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves",

main steam line drain valves" and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests to less than or equal to 0.60 L

, and a'.

The leakage rate to less than or equal to 46 scf per hour for all four main steam lines through the isolation valves, and d.

The leakage rate to less than or equal to 1.2 scf per hour for any one main steam line drain valve, and e.

The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 200'F.

SURVEILLANCE RE UIREMENTS 4.6. 1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the cr'iteria specified in Appendix J of 10 CFR 50 using the methods and provis'ions of ANSI N45.4 - 1972:

a 0 b.

c ~

Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 + 10 month intervals during shutdown at P

45.0 psig, during each 10-year service period.

The third te3t of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

If any periodic Type A test fails to meet

.75 L

, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet.75 L,

a Type A test shall be per'formed at least every 18 months until tlo consecutive Type A tests meet

. 75 L

, at which time the above test schedule may be resumed.

The accuracy of each Type A test shall be verified by a supplemental test which:

2.

3.

Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L..

a'as duration sufficient to establish accurately the change in leakage rate. between the Type A test and the supplemental test.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P

, 45.0 psig.

SUSQUEHANNA -.UNIT 1 3/4 6-3

CONTAINMENT SYSTEMS

~SURVEILLANCE RE UIREMENTS Continued) d.

Type B and C tests shall be conducted with gas at P

, 45.0 psig," at intervals no greater than 24 months except for test3 involving:

1:

Air locks, 2

Main steam line isolation valves and main steam line drain

valves, 3.

Containment isolation valves'n hydrostatically tested lines which penetrate the primary containment, and 4.

Purge supply and exhaust isolation valves with resilient material seals.

e.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6. 1.3.

Main steam line isolat',on valves and main steam line drain valves shall be leak tested at least once per 18 months.

g.

Containment isolation valves in hydrostatically tested lines which penetrate.the primary'containment shal'1 be leak tested at'least once per 18 months.

/

h.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6. 1.8.2.

i.

The provisions of Specification 4.0.2 are not applicable to 24 month or 40 2 10 month surveillance intervals.

Unless a hydraulic test is required per Table 3.6.3-1.

SUSQUEHANNA - UNIT 1 3/4 6-4 Amendm'ent No.

8

ELECTRICAL POMER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.3.l The following power distribution system divisions shall be energized with tie breakers open both between redundant buses within the unit and between units at the same station:

b.

2.

d)

Load group 208/120 volt A.C. instrument panels Division II, consisting of:

~ a)

Load group Channel"B", consisting of:

1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A.C. motor control center b)

Load group Channel "D", consisting of:

1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A.C. motor control center c)

Load group 480 volt A.C. motor control centers d)

Load group 208/120 volt A.C. instrument panels D.C.

power distribution:

1.

Division I, consisting of:

a)

Load group Channel "A", consisting of:')

125 volt DC buses 2)

Fuse box b)

Load group Channel "C", consisting of:

1) 125 volt DC buses 2)

Fuse box c)

Load group "I", consisting of:

1) 250 volt DC buses 2)

Fuse box d)

Load group "I", consisting of:

1)

+ 24 volt DC buses 2)

Fuse box A.C. power distribution:

1.

Division I, consisting of:

a)

Load group Channel "A", consisting of:

1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A. C.

motor contr ol center b)

Load group Channel "C", consisting of:

1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A.C. motor control center c)

Load group 480 volt A.C. motor control centers 1A201 1B210 OB516 1A203 1B230 OB536

OB517, OB136

18216, 1B236

1B217, 1B237 1B219

1Y216, 1Y236

, 1A202 1B220 OB526 lA204 1B240 OB546

OB527, OB146

18226, 18246

18227, 18247 1B229

1Y226, 1Y246

1D612, 10614 10611

1D632, 1D634 1D631

1D652, 1D254 1D651 1D672 1D671 SUSQUEHANNA - UNI$ 1 3/4 8-17

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ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION Continued ACTION:

(Continued)

D.C. power distribution:

(Continued) 2.

Division II, consisting of:

a)

Load group Channel "B" consisting of:

1) 125 volt DC buses 2)

Fuse box

10622, 10624 10621 b)

Load group Channel "D" consisting of:

1) 125 volt DC buses 2)

Fuse box c)

Load group "II". consisting of:

1) 250 volt DC buses

')

Fuse box

- d)

Load group "II" consisting of,:

1)

+ 24 volt DC buses 2)

Fuse box t APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

10642, 10644 10641

16662, 16264, 16274 1D.661 10682 10681 a.

b.

With one of the above required A.C. distribution system load groups not energized, re-energize the load group within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 .

t With one of the above required D.C. distribution system load groups not energized, re-energize the load group within P hours 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 .

SURVEILLANCE RE UIREMENTS 4.8.3.

1 Each of the above required power distribution system load groups shall be determined 'energized at least once per 7 days by verifying correct breaker alignment and voltage on the busses/MCCs/panels.

SUSQUEHANNA - UNIT 1 3/4 8-18 Amendment No.

8

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION

3. 11.2.6 The concentration of hydrogen or oxygen in the main condenser offgas treatment system shall be limited to less than or equal to 4X by volume.

APPLICABILITY: Whenever the main condenser air ejector (evacuation) system is in operation.

ACTION:

a 0 b.

With the concentration of. hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by continuously monitoring the waste gases in the main-condenser offgas treatment system with the hydrogen monitors required OPERABLE by Table 3.3.7. 11-1 of Specification

3. 3.7. 11.

SUSQUEHANNA " UNIT 1 3/4 11-17

RADIOACTIVE EFFLUENTS MAIN CONDENSER LIMITING CONDITION FOR OPERATION

3. 11.2.7 The radioactivity rate of the noble gases Kr-85m, Kr-87, Kr-88, Xe-133, Xe-135, and Xe-138 measured at the motive steam jet condenser discharge shall be limited to less than or equal to 330 millicuries/second.

APPLICABILITY:

OPFRATIONAL CONDITIONS 1, 2* and 3*.

ACTION:

With the gross radioactivity rate of the specified noble gases at the motive steam jet condenser discharge exceeding 330 millicuries/second, restore the gross radioactivity rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE UIREMENTS

4. 11.2.7.

1 The radioactivity rate of noble gases at the motive steam jet condenser discharge shall be continuously monitored in accordance with Specification 3.3.7.

1 l.

4. 11.2'.2 The gross radioactivity rate of the specified noble gases from the motive steam jet condenser discharge shall be determined to be within the limits of Specification 3.11.2.7 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the discharge:

'a 0 b.

At least once per 31 days.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an increase, as indicated by the Condenser Offgas Pre-Treatment Radioactivity Monitor, of greater than 50X, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant.

When the main condenser air ejector is in operation.

SUSQUEHANNA - UNIT 1 3/4 11-18 Amendment No.

8

ML17139B355

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