ML19305D092

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Amend 26 to License DPR-66 Adding Condition Requiring Secondary Water Chemistry Monitoring Program & Changing Tech Specs to Prohibit Containment Purge by Steam Jet Air Ejector Sys During Hot Shutdown
ML19305D092
Person / Time
Site: Beaver Valley
Issue date: 02/29/1980
From: Schwencer A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19305D093 List:
References
NUDOCS 8004140054
Download: ML19305D092 (15)
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UNITED STATES

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g NUCLEAR REGULATORY COMMISSION

p WASHINGTON, D. C. 20555

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DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. OPR-66 1.

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

A.

The applications for amendment by Duquesne Light Conpany, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated September 28, 1979 and December 5,1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; i

D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. 6The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been s'atisfied.

8004140g3Q

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,.2.

Accordingly, the license is amended by changes to the Technical Specifications as indicr.d in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as fallows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 26, are hereby incorporated in the license.

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

i 3.

In addition, the licensee is hereby amended to include the following paragraph:

2.C.(9) The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degrad-ation.

This program shall be described in the station chemistry manual and shall include:

t j

1.

Identification of sampling schedule for the critical parameters and control points for these parameters; 2.

Identification of the procedures used to measure the values of the critical parameters; 3.

Identification for process sampling points; 4.

Procedure for the recording and management of data; 5.

Procedures defining corrective actions for off control point chemistry conditions; and 6.

A procedure identif.ying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION yNY$h A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance; February 29, 1980

ATTACHMENT TO LICFt.'SE AMENDMENT NO. 26 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the followino pages of the Appendix "A" Technical Specifications with the enclosed page. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The correspondina overleaf pages are also provided to maintain document completeness.

Remove Paaes Insert Paaes VII VII 3/4 6-lod 3/4 6-19d 3/4 6-19f 3/4 6-19f 3/4 6-25 3/4 6-25 3/4 7-10a 3/4 7-10b B 3/4 7-3 B 3/4 7-3 R 3/4 7-4 B 3/4 7-4 i

t 1

l l

I i

E i

r

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves..........................................

3/4 7-1 Auxil i a ry Feedva ter Pumps..............................

3/4 7-5 Prima ry Plant Demineral ized Water......................

3/4 7-7 Activity...............................................

3/4 7-8 Main Steam Line Isola tion Va1 ves.......................

3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........

3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM.........................

3/4 7-12 3/4.7.4 RIVER WATER SYSTEM.....................................

3/4 7-13 3/4.7.5 ULTIMATE HEAT SINK.....................................

3/4 7-14 3/4.7.6 FLOOD PROTECTION.......................................

3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS............

3/4 7-16 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM........

3/4 7-19 3/4.7.9 SEALED SOURCE CONTAMINATION............................

3/4 7-22 3/4.7.10 RESIDUAL HEAT REMOVAL SYSTEM T,yg >,350 F..............

3/4 7-24 3/4.7.11 RESIDUAL HEAT REMOVAL SYSTEM T,yg < 350*F..............

3/4 7-25 3/4.7.12 HYDRAULIC SNUBBERS.....................................

3/4 7-26 3/4.7.13 AUXILIARY RIVER WATER SYSTEM...........................

3/4 7-34 3/4.7.14 FIRE SUPPRESSION SYSTEMS Fire Suppre,ssion Water System..........................

3/4 7-35 S p r i n kl e r Sys tems......................................

3/4 7-39 6

Low Pressure CO Sy s t em..........'......................

3/4 7-41 2

F i re Ho s e S ta ti o n s.....................................

3/4 7-42 3/4.7.15 P EN ET RAT I O N F I R E BA R R I E RS..............................

3/4 7-44 r

BEAVER VALLEY - UNIT 1 VII Amendment No. 2, E, JJ, 26

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0 pe ra ti n g..............................................

3/4 8-1 Shutdown...............................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Di st ri bution - Operati ng..........................

3/4 8-6 A.C. Distribution -

Shutdown...........................

3/4 8-7 D.C. Distribution - Operating..........................

3/4 8-8 D.C. Distribution - Shutdown...........................

3/4 8-10 i

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON C0NCENTRAT10N....................................

3/4 9-1 l

3/4.9.2 INSTRUMENTATION........................................

3/4 9-2 i

P 3/4.9.3 DECAY TIME.............................................

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................

3/4 9-4 3/4.9.5 COMMUNICATIONS.........................................

3/4 9-S t

3/4.9.6 MANIPULATOR CRANE OPERABILITY..........................

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING........

3/4 9-7 3/4.9.8 COOLANT CIRCULATION....................................

3/4 9-8 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.........

3/4 9-9

/

L BEAVER VALLEY - UNIT 1 VIII Amendment No. 23

\\

TABLE 3.6-1 (Continued)

ISOLATION TIME gg VALVE NUMBER TESTABLE DURING (Sec)

INSIDE/0UTSIDE FUNCTION PLANT OPERATION INSIDE/0UTSIDE

.u 5.

l-C.

Containment Purge and Exhaust Q

1.

VS-D-5-3R VS-D-5-3A Containment Purge Exhaust No 8

8 2.

VS-D-5-5B VS-D-5-5A Containment Puroe Supply No 11 8

c

,3.

VS-D-5-6 Containment Purge Vacuum Breaker No N/A N/A 2

.a

a5 D.

Manual 1.

ICH-181 MOV-CH308A Seal Injection Water to RC Pump No N/A N/A o

2.

ICH-182 MOV-CH308B Seal Injection Water to RC Pump No N/A N/A 3.

ICH-183 MOV-CH3n8C Seal Injection Water to RC Pump No N/A N/A

  • 5.

MOV-CCll283 1CCR-252 CCW from RHR Hx & RHR Pump Seal Coolers Yes N/A N/A

  • 6.

MOV-CCll2A3 1CCR-251

. CCW from RHR Hx & RHR Pump Seal Coolers Yes N/A N/A

  • 7.

MOV-CCll2A2 1CCR-247 CCW to RHR Hx A RHR Pump Seal Coolers Yes N/A N/A

  • 8.

ft0V-CCll2B2 1CCR-248 CCW to RHR Hx % RHP Pump Seal Coolers Yes N/A N/A 3

89.

M0V-FW-151 A Auxiliary Feedwater Yes.

N/A N/A g-

  1. 10.

MOV-FW-151B Auxiliary Feedwater Yes N/A N/A

  1. 11.

MOV-FW-151C Auxiliary Feedwater Yes N/A N/A

  1. 12.

MOV-FW-151 D Auxiliary Feedwater Yes

'N/A N/A g

  1. 13.

MOV-FW-151E Auxiliary Feedwater Yes N/A N/A 314.

MOV-FV-151 F Auxiliary Feedwater Yes N/A N/A y

31 5.

MOV-RW104A Riverwater to Recirc. Spray Hx Yes N/A N/A

  1. 16.

M0V-RW104C Riverwater to Recire. Spray Hx Yes N/A N/A C$

e17.

MOV-RWin4B Riverwater to Recirc. Sprav HX Yes N/A N/A

  1. 18.

MOV-RW104D Riverwater to Recric. Spray Hx Yes N/A H/A

TARLE 3.6-1 (Continued) -

h ISOLATION TIME M

TESTABLE DURING (Sec)

VALVF N!!MRE_R INSI0t/Oliis10E FilNCTION PLANT OPERATION INSIDE/0UTSIDE x

g g

  1. 19.

H0V-RW105A D.iverwater from Recirc. Soray Hx Yes N/A N/A F

  1. 2n.

MOV-Ruln5C Riverwater from Recirc. Soray Hx Yes N/A N/A

  1. 21.

40V-RWin58 Riverwater from Recirc. Spr~ay Hx

-Yes N/A N/A z

  1. 22.

40V-Rul05n D.iverwater from Recire. Spray Hx Yes N/A N/A c

-4

23. 1SI-83 MnV-SIR 60A Hiah Head SI to Hot leg No N/A N/A
24. 15.I-84 MnV-SI8698 Hioh Head SI to Hot Leo No N/A N/A 25.

MOV-SI800A Low Head SI No N/A N/A 2A.

MOV-SI800C Low Head SI No 4/A N/A No N/A N/A 27.

MOV-SI8908 Low Head SI

28. 1SI-95 MnV-SI836 Hinh Head SI to Cold Leas No N/A N/A 24 40V-SI860A low Head SI Dumn Suction from Cont. Sumo Yes N/A N/A 30 MnV-SI860R Low Head SI Dump Suction from Cont. Sumo Yes N/A N/A No N/A N/A g
  • 31.

1CH-170 FCV-CH160 RCS Fill

  • 32.

151-41 SIAccumulator Makeuo Yes N/A N/A Yes N/A N/A' m

33.

1RH-14 1RH-15 RHR to quST L

34. HCV-CV-151 HCV-CV-151-1 Containment Vacuum Fiector Suction Yes N/A N/A
  • 35.

1PC o IPC-10 Reactor Cavity Purification - Inlet Yes N/A N/A 36.

1PC-37 1PC-38 Reactor Cavity Purification - Outlet Yes N/A N/A 37.

1SA-14 Comoressed Air to Fuel Handlino Eauipment Yes N/A N/A No N/A N/A 38.

lIA-90 Instrument Air Press Dead w icht Calibrator Yes N/A N/A e

  • 39 1-RC277 1-RC278f.M(2)]

y aq.

lHY-lll H Recombiner Discharoe to Containment Yes N/A N/A g

41.

lHY-110 H Recombiner Discharoe to Containment Yes N/A N/A O leted g

  1. 43.

40V-MS-105 Steam to Aux. Feed Dumo Yes N/A N/A g-42.

Deleted r*

44.

Deleted 2

45.

Containment Leakaoe Monitorino - Sealed Yes N/A N/A P

A6 1CV-36 System Cont. Vaccum Pump f. H Recomb. Suct.

Yes N/A N/A w

47.

lHY-102 y

Cont. Vacuum Pumo A H Recomb. Suct.

Yes N/A N/A lHY-104 N

48.

1HY-101 m

lHY-103

TABLE 3.6-1 (Continued)

ISOLATION TIME VALVE NUMB'ER TESTABLE DURING (Sec)

INSIDE/0UTSIDE FUNCTION PLANT OPERATION INSIDE/0UTSIDE 9gj 49.

ICV-35 Containment Leak. Monit. - Sealed Sys.

Yes N/A N/A x

50. 1AS-278 Main Condenser Ejector Vent No N/A N/A g
51. 1QS-4 Ouench Spray Pump - Discharge No N/A N/A p-
52. 1Q5-3 Quench Spray Pump - Discharge No N/A N/A p
53. 1RS-101

-Outside Recirc. Spray - Discharge No N/A N/A

54. 1RS-100 Outside Recirc. Spray - Discharge No N/A N/A
55. ICH-31 Reactor Coolant System Charging No N/A N/A 5
56. ISI-10 Low Head SI No N/A N/A c:.

-d

57. ISI-ll Low Head SI No N/A N/A
58. 1SI-12 Low Head SI No N/A N/A

~

59. ISI-13 ISI-451 Low Head SI No N/A N/A
60. ISI-14 Low Head SI No N/A N/A 61.

ISI-452 Low Head SI No N/A N/A

62. lHY-119 H Recombiner Discharge To Containment No N/A N/A
63. 1HY-120 H2 Recombiner Discharge To Containment

' No N/A N/A' 2

64. 151-42 SI Accumulator Makeup No N/A N/A 4d
65. ISA-15 Compressed Air to Fuel Handling Equipment No N/A N/A
66. 11 A-91 Instrument Air No N/A N/A T
67. IRC-68 Nitrogen to Pressurizer Relief Tank No N/A N/A g
68. ICH-369 Reactor Coolant Pump Seal Water Return No N/A N/A
69. IRC-72 Primary Grade Water to Pressurizer Relief Tank No N/A N/A 70.1SI-94 Baron Injection (High Head SI to Cold Leg)

No N/A N/A

  • 71.

1SI-91 Boron Injection (High Head SI to Cold Leg)

Yes N/A N/A 72.

ISI-447 Low Head 3afety Injection System From Containment Sump No N/A N/A 73.

1SI-448 Low Head Safety Injection System From Containment Sump No N/A N/A 2f

74. IRH-16 Return to Pool Purification Pumps No N/A N/A
75. RV-CH-203 Letdown Relief to Pressurizer Relief Tank No N/A N/A f

E' E.

Safety Injection (SIS) e

!?

1.

MOV-CH289 Reactor Coolant System Charging Yes N/A 15 2.

M0V-SI867C Boron Injection - High Head SI to Cold Legs Yes N/A 15 MOV-SI8670

TARLE 1.6-1 (Continued)'

E ISOLATION TIME 9

VALVE NilMBER TESTABLE OllRING (Sec) g INSIDE/OllTSIDE FUNCTION PLANT OPERATION INSIDE/0UTSIDE h ~ F.

Steam I-ine Isolation (SLI)

TV MS101A Main Steam No N/A 5

[' #1. ~

z-

  1. 2.

TV-MS101B Main Steam No N/A 5

Z

  1. 3.

TV MS-101C Main Steam No N/A 5

  1. 4 TV MS-lllA Main Steam Line Grain' Yes N/A 10
  1. 5.

TV-MS-lllB Main Steam Line Orain Yes N/A 10 46.

TV-MS-lllC Main Steam Line Orain Yes N/A 10 R.

11 Feedwater Isolation

.o No N/A 75

?

  1. 1.

MnV-FF156A Feedwater No N/A 75 g

  1. 2.

MOV-FHl56B Feedwater

  1. 3.

40V-Ful56C Feedwater No N/A 75 -

  1. d.

FCV-FW478 Feedwater Flow Control No' N/A 10

  1. 5.

FCV-FWa88 Feedwater Flow Control No N/A 10 46.

FCV-FW408 Feedwater Flow Control No N/A

-10 H.

Containment Air Lock (Manual)

E Yes N/A

  • l.

SOV-1VS-1 Eoualization Valve

  • 2.

SOV-lVS-2 Eoualization Valve Yes N/A Yes N/A

    1. 3.

SOV-lVS-5 Enualization Valve Yes N/A

  • Aa.

SOV-lVS-6 Eoualization Valve J

    1. 5.

IVS-151 Manual Eoualization Block Yes N/A T

  • May be onened on an intermittent basis under administrative control.

g

  1. Not subject to Type C leakaoe tests.

CONTAINMENT SYSTEMS 3/4.6.5 S'JBATMOSPHERIC PRESSURE CONTROL SYSTEM STEAM JET AIR EJECTOR LIMITING CONDITION FOR ODERATION 3.6.5.1 The inside and outside manual isolation valves in the steam jet 4

air ejector suction line shall be closec.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

Pith the inside or outside manual isola' tion valve in the steam jet air efector suction line not closed, restore the valve to the closed position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLO SHUTDOWN within the followino 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

t SilRVEILLANCE REQUIREMENTS 4.6.5.1.1 The steam jet air ejector suction line outside manual isolation valve shall be determined to be in the closed position by a visual inspection prior to increasing the Reactor Coolant System temperature above 350 F and at least once oer 31 days thereafter, a.6.5.1.2 The steam jet air ejector suction line inside manual isolation valve shall be determined to be sealed or locked in the closed position by a visual inspection prior to increasing the Reactor Coolant System temperature above 350 F.

I BEAVER VALLEY - UNIT 1 3/4 6-25 Amendmurt No. 26

CONTAINMENT SYSTEMS MECHANICAL VACUUM PUMPS LIMITING CONDITION FOR OPERATION 3.6.5.2 Two mechanical vacuum pumps shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one mechanical vacuum pump inoperable, restore the inoperable pump to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 />.

SURVEILLANCE REQUIREMENTS 4.6.5.2 Each mechanical vacuum pump shall be demonstrated OPERABLE at least once per 31 days on a STAGGERED TEST BASIS by:

Starting (unless already operating) each pump from the control a.

room, b.

Verifying that each pump develops a pumping capacity of > 4 SCFM and. discharges to the gaseous radwaste disposal system, i

, c.

Verifying that each pump operates for at least 15 minutes.

i BEAVER VALLEY - UNIT 1 3/4 6-26 L

PLANT SYSTEMS t

BASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line.

These values are consistent with the assumptions used in the accident analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.

The OPERABILITY of the main steam isolation valv7s within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.

\\

BEAVER VALLEY - UNIT 1 B 3/4 7-3 Amendment No. 3,26 l

I

.~

b PLANT SYSTEMS BASES 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70 F and 200 psig are based on a steam generator average impact values taken at 10*F and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.

The redundant cooling capacity uf this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

3/4.7.4 RIVER WATER SYSTEM The OPERABILITY of the river water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.

The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions.

3/4.7.5 ULTIMATE HEAT S!NK l

The limitations on the ultimate heat sink level and temperature normal cooldown of the facility, or 2)y is available to either 1) provide ensure that sufficient cooling capacit i

to mitigate the effects or accident conditions withi'n acceptable limits.

i The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is i

consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants."

3/4.7. 6 FLOOD PROTECTION The limitation on flood level ensures that facility operation will be terminated in the event of flood conditions. The limit of elevaticn 695 Mean Sea Level was selected on an arbitrary basis as an appropriate flood level at which to terminate further operation and initiate flood protection measures for safety related equipment.

BEAVER VALLEY - UNIT 1 B 3/4 7-4 Amendment No. 3, 26

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