ML17251A585

Amend 13 to License DPR-18,providing New Limiting Condition of Operation & Surveillance Requirements for 48-inch Purge Sys & 8-inch mini-purge Sys

ML17251A585
Person / Time
Site:	Ginna
Issue date:	02/15/1986
From:	Lear G Office of Nuclear Reactor Regulation
To:
Shared Package
ML17251A586	List: ML17251A585 ML17251A587
References
NUDOCS 8602240176
Download: ML17251A585 (18)

Text

gp,R REOgp (4

~4 0

Cy o Q

'+n gO

++**+

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.

E.

GINNA NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

13 License No.

DPR-18 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated October 22, 1985, modified December 23, 1985 and supplemented January 8,

1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and 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 with the Commission's regulations; D.

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.

8602240i76 8602' PDR ADOCK 05000244, PDR ~

I

~

~

l l

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license

.c amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-18 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 13, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 15, 1986 G orge E. Lear, irector Project Directorate 81 Division of PWR Licensing-A, NRR

ATTACHMENT TO LICENSE AMENDMENT NO.

13 FACILITY OPERATING LICENSE NO. DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised. pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE 3.5-22 3.6-2 3.6-5 3.6-6 3.6-7 3.6-11 3.8-1 4.4-7 4.4-8 INSERT 3.5-22 3.6-2 3.6-5 3.6-6 3.6-7 3.6-7A 3.6-11 3.8-1 4.4-7 4.4-8 4.4-8A

1

I I

TABLE 3.5-7 Radiation Accident Monitorin Instrumentation Instrument 1.

Containment Area (R-29 and R-30) 2.

Noble Gas Effluent Monitors i.

Plant Vent (R-14) ii.

A Main Steam Line (R-31) iii. B Main Steam Line (R-32) iv..

Containment Purge (R-12A) v.

Air Ejector (R-15A)

Minimum Channels

~ereble Action Action Statements Action 1 - With the number of operable channels less than required by the Minimum Channels Operable requirements, either restore the inoperable channel(s) to operable status within 7 days of the event, or prepare and submit a Special Report to the Commission within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

only when the shutdown purge system flanges are removed.

3.5-22 Amendment No. 9, 13

3.6.3 3.6.3.1 Containment Isolation Valves With one or more of the isolation valve(s) specified in Table 3.6-1 inoperable, maintain at least one isolation valve operable in each affected penetration that is open and either:

a.

Restore the inoperable valve(s) to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.

c ~

d.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind'lange, or Be in at least hot shutdown within the next 6

hours and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3.6.4 3.6.4.1 3.6.4.2 Isolation valves are inopeable from a leakage standpoint if the leakage is greater than that allowed by 10 CFR 50 Appendix J.

Combustible Gas Control When the reactor is critical, at least two independent containment hydrogen monitors shall be operable.

One of the monitors may be the Post Accident Sampling System.

With only one hydrogen monitor operable, restore a

second monitor to operable status within 30 days or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

3.6.4.3 With no hydrogen monitors operable, restore at least one monitor 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 be at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

3.6.5 Containment Mini-Pur e Whenever the containment integrity is required, emphasis will be placed on limiting all purging and venting times to as low as achievable.

The mini-purge isolation valves will remain closed to the maximum extent practicable but may be open for pressure control, for ALARA, for respirable air quality consider-ations for personnel entry,. for surveillanoe tests that require the valve to be open or other safety related reasons.

• Becomes effective upon installation of containment mini-purge valves 3.6-2 Amendment No.

9, 13

PENT.

NO.

121 121 121 121 123 124 124 125 126 127 128 g.

129 130 0

131 132 140 IDENTIFICATION/DESCRIPTION Nitrogen to PRT Reactor Makeup water to PRT Cont. Press.

transmitter PT"945 (10)

Cont. Press.

transmitter PT-946 (10)

Reactor Coolant Drain Tank (RCDT) to GA Excess letdown supply and return to heat exchanger Post. Accident air sample "C" fan Component Cooling Water (CW) from 1B RCP COW from 1A RCP CCW to 1A RCP COW to 1B RCP RCDT 8 PRT to Vent Header CCWi to 'reactor support cooling I

COW to reactor support cooling ISOLATION BOUNDARY CV 528 CV 529 PT 945 PT 946 AOV 1789 AOV 745 CV 743 MV 1569 MV 1572 MOV 759B MOV 759A CV 750A CV 750B AOV 1787 CV 1713 MOV 813 MOV 814 RHR pump suction from "A" Hot leg MOV 701(20)

Mini-Purge exhaust [Depressurization at P ower) AOV 7970 l

1 MAXIMUM ISOLATION TIME +(SEC)

NA NA NA NA 60 60 NA ISOLATION BOUNDARY MV 547(8)

AOV 508 MV 1819A MV 1819B MV 1655(7)

NA NA NA NA NA NA 60 NA 60 60 MV 1571 HV 1574 (12)

(12)

MOV 749A MOV 749B AOV 1786 (19)

(19)

NA (6) 5 [60]

AOV 7971 MAXIMUM ISOLATION TIME +(SEC)

NA 60 NA NA NA NA NA NA NA NA NA 60 60 60 NA

~

~

~

NA 5 [6O)

(23)

NA

PENT.

NO.

141 142 143 IDENTIFICATION/DESCRIPTION RHR-81 pump suction from Sump B

RHR-g2 pump suction from Sump B

RCDT pump suction I

I ISOLATION BOUNDARY MOV 850A(13)

MOV 850B(13)

AOV 1721 I

1 MAXIMUM ISOLATION TIME *(SEC)

NA NA 60 ISOLATION BOUNDARY MOV 851A(13)

MOV 851B(13)

AOV 1003A AOV 1003B MAXIMUM ISOLATION TIME *(SEC)

NA NA 60 60 201 Reactor Compart. cooling Unit A 8 B 202 "B" Hydrogen recombiner (pilot 8 main) 203 Post accident air sample to "B" fan 203 Contain, Press.

transmitter PT-947 8 948 MV 4757(16)

MV 4636(16)

MV 1076B MV 1084B PT 947 PT 948 MV 1563 MV 1566 NA NA NA NA NA NA NA NA NA NA MV 1819C MV 1819D MV 1565 MV 1568 NA NA NA NA SOV IV-3B NA Normally Closed SOV IV-5B NA Normally Closed 204 205 206 206 207 207 209 Shutdown Purge Supply Duct[Purge Supply Hot leg loop sample Przr. liquid space sample "A" S/G sample Prtr. Steam space sample I

"B" S/G sample Reactor Compart. cooling Units A 8 B Duct] flange (22)

AOV 5870]

OV 966C AOV 966B AOV 5735 AOV 966A AOV 5736 MV 4758(16)

MV 4635(16) 60 60 60 60 60 NA NA MV 956D(14)

MV 956K(14)

HV 5733(7)

MV 956F MV 5734(7)

~

~ -

~

I y

~

~

NA

[5]

AOV 5869 (22)

NA NA NA NA NA NA NA 210 Oxygen makeup to A 6 B recombiners MV 1080A l

NA SOV IV-2A SOV IV-2B NA Normally Closed NA Normally Closed

PENT.

NO.

IDENTIFICATION/DESCRIPTION ISOLATION BOUNDARY I

l MAXIMUM ISOLATION TIME *(SEC)

ISOLATION BOUNDARY MAXIMUM ISOLATION TIME *(SEC) 300 301 303 304 305 I

Shutdown Purge Exhaust Duct[purge Exhaust Duct]

Aux. steam supply to containment Aux. steam condensate return "A" Hydrogen recombiner (pilot and main)

Radiation Monitors R-ll, R-12 8 R"10A Auto Inlet Isol.

flange (22)

[AOV 5878]

MV 6151 MV 6175 MV 1084B MV 1076A AOV 1597 NA NA NA NA 60 MV 6165(15)

MV 6152(15)

SOV IV"5A SOV IV-3A MV 1596 NA [5]

AOV 5879 (22)

(24)

NA NA

~

NA Normallly Closed NA Normallly Closed NA 305 305 R-ll, R-12 6 R-10A Outlet Post Accident air sampler (containment)

AOV 1599 MV 1554 MV 1557 MV 1560 60 NA NA NA AOV 1598 MV 1556 MV 1559 MV 1562 60 60 NA NA 307 308 309 g

310 o

310 311 312 313 Fire Service Water Service Water to "A" fan cooler Mini-Purge supply

[Leakage Test Depressurization]

Service Air to Contain.

Instrument Air to Contain.

I Sehrice Water from "B" fan cooler Service Water to "D" fan cooler Leakage test depressurization CV 9229 MV 4627(16)

NA NA AOV 9227 CV 7226 CV 5393 MV 4630(16)

MV 4642(16) flange NA NA NA NA NA MV 7141 AOV 5392 MOV 7444 AOV 7478

[Flange]

5 [NA]

AOV 7445 (18)

NA

[MOV 7445] 5 [NA normally closed]

NA 60 NA l

NA l

NA Normally Closed

PENT.

NO.

315 316 317 318 319 320 I

321 322 323 324

". 332 D

332 IDENTIFICATION/DESCRIPTION Service Water from "C" fan cooler Service Water to "B" fan cooler Leakage test supply Dead weight tester (decomissioned)

Service Water from "A" fan cooler Service water to "C" fan cooler A S/G Blowdown.

B S/G Blowdown Service Water from "D" f'an cooler Demineralized water to Containment Cont. Press.

Trans.

PT-944, 949 8 950 Leakage test and hydrogen monitor instrumentation lines MV 4643(16)

MV 4628(16) flange welded shut MV 4629(16)

MV 4647(16)

AOV 5738 AOV 5737 MV 4644(16)

CV 8419 PT 944 PT 949 PT 950 MV 7448 MV 7452 MV 7456 SOV 921 SOV 922 SOV 923 SOV 924 NA NA NA NA NA NA 60 60 NA NA NA NA NA NA NA NA NA NA NA NA I

1

~

i '

MAXIMUM ISOLATION ISOLATION BOUNDARY TIME +(SEC)

ISOLATION BOUNDARY MAXIMUM ISOLATION TIME *(SEC)

NA NA MOV 7443 welded shut NA NA MV 5701(7)

MV 5702(7)

AOV 8418 MV 1819G MV 1819F MV 1819E cap cap cap (21)

(21)

(21)

(21)

~

~

~

~

I

~

~

)

.II NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Normally Closed wA 0

(21) Acceptable isolation capability is provided for instrument lines by two isolation boundaries outside containment.

One of the boundaries outside containment may be a Seismic Class 1 closed system which is subjected to Type C leak xate testing.

(22) The flanges at penetrations 204 and 300 can only be removed at cold or refueling shutdown.

The flanges and associated double seals provide containment isolation and are a containment boundary for all modes of operation between cold shutdown and normal operation.

During cold and refueling shutdown when the flanges are removed integrity is provided by the 48 inch valves.

(23)

Items in square brackets are effective until the installation of the new containment mini-purge valves for penetration Nos.

132 and 309.

At that time, they are replaced by mini-purge line items as identified.

(24)

Items in square brackets are effective until the installation of the flanges that cbnvert the containment purge system to the containment shutdown purge system for penetration Nos.

204 and 300.

At that time they are replaced by shutdown purge system line items as identified.

3.6-11 Amendment No.

13

REFUEL ING

~1 I

Applies to operating limitations during refueling operations.

To ensure that no incident could occur during -refueling operations. that would affect public health and safety.

Rl During refueling operations the following conditions shall be satisfied.

a

~

b.

c ~

The equipment door, or a closure plate that restricts air flow from the containment, and at least one personnel door in the equipment door or closure plate and in the personnel air lock shall be properly closed.

In addition, all automatic containment isolation valves shall be operable or at least one valve in each line shall be locked closed.

The 48 inch shutdown purge valves must also be operable or closed or the associated flange must be installed.

Radiation levels in the containment shall be monitored continuously.

Core subcritical neutron flux*shall be contin-uously monitored by at least two source range neutron monitors, each with continuous visual indication in the control room and one with S

audible indication in the containmentmnd control room available whenever core geometry is being changed.

When core geometry is not being changed at, 3.8-1 Amendment No. g, 13

shutdown and depressurized until repairs are effected and the local leakage meets the acceptance I

criterion.

c Ifit is determined that the leakage through a

mini-purge supply and exhaust line is -greater than 0.05 L an engineering evaluation shall be performed and plans for corrective action developed.

4.4.2.4 Test Fre enc a 0 b.

Except as specified in b., c.,

and d. below, individual penetrations and containment isolation valves shall be tested during each reactor shutdown for refueling, or other convenient

~

intervals, but in no case at intervals greater than two years.

In addition, the four mini-purge isolation valves shall be tested at six month intervals.*

The containment equipment hatch, fuel transfer

tube, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.

• (This requirement is applicable for two years following installation of the mini-purge system).

• • Becomes effective upon the installation of the containment mini-purge valves.

4.4-7 Amendment No.

13

c ~

The containment air locks shall be tested at I

intervals of no more than six months by pressurizing the space between the air lock doors.

In addition, following opening of the air lock door duzing the interval, a test shall be performed by-pressurizing between the dual seals of each door opened, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the opening, unless the reactor was in the cold shutdown condition at the time of the opening or has been subsequently brought to the cold shutdown condition.

A test shall also be performed by pressurizing between the dual seals of each door within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of leaving the cold shutdown condition, unless the doors have not been open since the last test performed either by pressurizing the space between the air lock doors or by pressurizing between the dual door seals.

r d.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing when containment integrity is required, except when being used for multiple cycles and'then at least once per 72

hours, each containment purge isolation valve shall be tested to verify that when the measured leakage rate is added to the leakage rates deter-mined for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 La

• This paragraph may be deleted upon installation of the containment shutdown purge system flanges.

4.4-8 Amendment No.

13

4.4.3 Recirculation Heat Removal S stems 4.4.3.1 Test

'a ~

b.

The portion of the residual heat removal system that is outside the containment shall-either be tested by use in normal operation or hydrostati-cally tested at 350 psig at the interval specified in 4.4.3.4.

Suction piping from containment sump B to the reactor coolant drain tank pump and the discharge piping from the pumps to the residual heat removal system shall be hydrostatically tested at no less that 100 psig at the interval specified in 4.4.3.4.

4 '-8A Amendment No 13