Text

Amend 11 to License DPR-72,revising Apps a & B,Tech Specs. Resolves Conflicting Requirements Re Reactor Bldg Purge Exhaust Duct Monitor Trip Setpoints & Amplifies Emergency Feedwater Pump Surveillance Requirement
	ML19317G521
Person / Time
Site:	Crystal River
Issue date:	01/11/1978
From:	Reid R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19317G519	List: ML19317G518; ML19317G521; ML19317G523; ML19317G528;
References
	NUDOCS 8003180812
	Download: ML19317G521 (17)
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UNITE D STATES I'

NUCLEAR REGULATORY COMMISSION

[,vQ.'.Q- (' j WASHINGTON, D. C. 20555

.g v

w ;/,.f FLORIDA PC'!ER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAltiESVILLE CITY OF KISSIPJiEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES C0fEISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES C0!NISSION AND CITY OF ORLAfD0 SEBRING UTILITIES COPJ4ISSION SEMIIiOLE ELECTRIC COOPERATIVE, INC.

CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, 11 License No. OPR-72 1.

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

A.

The application for amendment by Florida Power Corporation, et al (the licensees) dated July 15, 1977, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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 j

l E.

The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements

.have been satisfied.

8003180 h &

.. 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 Facility Operating License No. OPR-72 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.11, are hereby incorporated in the license.

Florida Power Corporation 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

' Y. N Robert ';. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 11, 1978 e

0 e

ATTACHMENT TO LICENSE AMENDMENT NO.11 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Pages 3/4 3-12 3/4 3-16 3/4 3-20 3/4 3-23 3/4 3-25 3/4 6-19 3/4 7-4 3/4 7-5

TABLE 3.3-3 (Cont'd)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION p

23 MINIMUM si TOTAL NO.

CHANNELS CHANNELS APPLICABLE

['

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

[j 3.

RCS Pressure Low-Low 3

2 2

1, 2, 3**

9#

[]

4.

Automatic Actuation Logic 2 1

2 1,2,3,4 10 2.

REACTOR BLDG. COOLING AND ISOLATION a.

Manual Initiation 2

1 2

1,2,3,4 13 os b.

Reactor Bldg. Pressure 30 liigh 3

2 2

1,2,3 9#

LJ';

c.

Automatic Actuation Logic 2

1 2

1,2,3,4 10 1

l i

~9 E%

-TABLE 3.3-3 (Cont'd) 51 j[

ENGINEERED SAFETY "EATURE ACTUATION SYSTEM INSTRUMENTATION US MINIMUM TOTAL NO.

CilANNELS CHANNELS APPLICABLE E

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION El.

)

3.

REACTOR BLDG. SPRAY w

a.

Reactor Bldg. Pressure liigh-liigh coincident with ilPI Signal 3

2 2

1,2,3 12 b.

Automatic Actuation Logic 2

1 2

1,2,3 10 w

12 4.

OTilER SAFETY SYSTEMS w

l.

a.

Reactor Bldg. Purge Exhaust Duct Isolation on liigh Radioactivity Gaseous 1

1 1

1, 2, 3, 4 11#

)

R 8

n md M

e e

TABLE 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION TRIP SETPOINTS n:o FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

[

1.

SAFETY IllJECTION 2

a.

High Pressure Injection ES

~

E!

Actuation "A" and "B" i

s; 1.

Manual Initiation Not Applicable

.Not Applicable Q

2.

Reactor Bldg. Pressure High 1 4 psig 1 4 psig 3.

RCS Pressure Low

> 1500 psig

> 1500 psig 4.

RCS Pressure Low-Low

> 500 psig

> 500 psig 5.

Automatic Actuation Logic Rot Applicable Kot Applicable b.

Low Pressure Injection ES Actuation "A" and "B" 1.

Manual Initiation flot Applicable Not Applicable

,g 2.

Reactor Bldg. Pressure High 1 4 psig i 4 psig 3.

RCS Pressure Low-Low

> 500 psig

> 500 psig 1,

4.

Automatic Actuation Logic Not Applicable Not Applicable m

2.

REACTOR BLDG. COOLING & ISOLATION a.

ES Actuation "A" and "B" 1.

Manual Initiation Not Applicable Not Applicable 2.

Reactor Bldg. Pressure High 1 4 psig 1 4 psig Not Applicable 3.

Automatic Actuation Logic Not Applicable b.

ES Actuation Indication "AB" 1.

Automatic Actuation Logic Not Applicable Not Applicable i

I TABLE 3.3-4 (Cont'd) n

o N

h ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION TRIP SETPOINTS P

h FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m

7 3.

REACTOR BLDG. SPRAY a.

Reactor Bldg. Pressure

)

High-High

$ 30 psig 1 30 psig H

coincident with HPI Signal See 1.a.2, 3, 4 See 1.a.2, 3, 4 w

b.

Automatic Actuation Logic Not Applicable Not Applicable 4.

OTHER SAFETY SYSTEMS a.

Reactor Bldg. Purge Exhaust Duct Isolation on High Radioactivity Gaseous Not Applicable l

w3 b.

Steam Line Rupture Matrix m'

_.m 1.

Low SG Pressure t 600 psig t 600 psig 2.

Automatic Actuation Logic Not Applicable Not Applicable

)

Fg R

e"

Determined by requirements of Appendix "B" Tech. Specs.'Section 2.4.2 - Crystal if River 3 Operating License No. DPR-72.

TABLE 4.3-2 (Cont'd)

E!

ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION SURVEILLANCE REQUIREMENTS "I

?:

CHANNEL MODES IN WHICH CilANNEL CHANNEL FUNCTIONAL SURVEILLANCE 2,

2 FUNCTIONAL UNIT CilECK CALIBRATION TEST REQUIRED 9

3.

RCS Pressure Low-Low S

R M

1,2,3 4.' Automatic Actuation Logic N/A

.N/A M(3) 1, 2, 3, 4 Z

2.

REACTOR BLDG. C0OLING AND u,

ISOLATION a.

flanual Initiation N/A N/A M(1) 1, 2, 3, 4 b.

Reactor Bldg. Pressure liigh S

R M(2) 1, 2, 3 c.

Automatic Actuation Logic N/A N/A M(3) 1, 2, 3, 4 u,2 3

g TABLE 4.3-2 (Cont'd)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION SURVEILLANCE REQUIREMENTS m

CHANNEL MODES IN WHICH 2

CilANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CllECK CALIBRATION TEST REQUIRED e

g 3.

REACTOR BLDG. SPRAY

~

r a.

Reactor Bldg. Pressure liigh-High coincident with ilPI Signal S

R M(4) 1, 2, 3 b.

Automatic Actuation Logic N/A N/A M(3) 1,2,3 4.

OTHER SAFETY SYSTEMS y

a.

Reactor Bldg. Purge Exhaust Duct Isolation on liigh Radioactivity Yg 1.

Gaseous S

Q M

All Modes l

b.

Steam Line Rupture Matrix 1.

Low SG Pressure N/A R

N/A 1,2,3 2.

Automatic Actuation Logic N/A N/A M(3) 1, 2, 3

)

3I m

r E

g TABLE 3.3-6 Dig RADIATION MONITORING INSTRUMENTATION r-m MINIMUM g

CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT m

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.

AREA MONITORS h

a.

Fuel Storage Pool Area

~3 4

1 15 mR/hr 10

- 10 mR/hr 14 1.

Criticality Monitor 1 m

2.

PROCESS MONITORS a.

Fuel Storage Pool Area 1.

Gaseous Activity -

Ventilation System 1

6 1 2 x background 10 - 10 cpm 16 Isolation 1

w2 b.

Reactor Building l

4 1.

Gaseous Activity -

a) Purge Exhaust Duct w

1 6

Isolation 1

6 10 - 10 cpm 17 b)

RCS Leakage 1

6 Detection 1

1, 2, 3 & 4 tiot Applicable 10 - 10 cpm 15 11.

Iodine Activity -

p RCS Leakage 6

g Detection 1

1, 2, 3 & 4 Not Applicable a,

- 10 cpm 15 k

With fuel in the storage pool or building 5

- With irradiated fuel in the storage pool

- - Determined by requirements of Appendix "B" Tech. Specs. Section 2.4.2 - Crystal River 3 2

P Operating License NO. DPR-72.

d t

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 14 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perfonm area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 15.-

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 16 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 17 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

I o

O 4

a CRYSTAL RIVER - UNIT 3 3/4 3-24

9 m

~

g TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

=

CHANNEL M005SINWHICH

~

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

,w INSTRUMENT CHECK CALIBRATION

~ TEST REQUIRED e

g 1.

AREA MONITORS G

a.

Fuel Storage Pool Area w

1.

Criticality Monitor S

R M

2.

PROCESS MONITORS a.

Fuel Storage Pool Area 1.

Gaseous Activity w2 Ventilation System Isolation S

R M

wL b.

Reactor Building 1.

Gaseous Ar:tivity -

a)

Purge Fxhaust Duct Isolation S

Q M

6 g

b)

RCS Leakage Detection S

R M

1, 2, 3, & 4 11.

Iodine Activity -

RCS Leakage

[j-Detection S

R M

1, 2, 3, & 4

With fuel in the storage pool or building E

- With irradiated fuel in the storage pool -

d

INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 As a minimum, the incore detectors shall be OPERABLE as specified

below, a.

For AXIAL POWER IMBALANCE measurements:

1.

Nine detectors shall be arranged such that there are three detectors in each of three strings and there are three detectors lying in the same axial plane with one plane at the core mid-plane and one plane in each axial core half.

2.

The axial planes in each core half shall be. symmetrical about the core mid-plane.

3.

The detector strings shall not have radial symmetry.

b.

For QUADRANT POWER TILT measurements with the Minimum Incore Detector System:

1.

Two sets of 4 detectors shall lie in each core half.

Each set of detectors shall lie in the same axial plane. The two sets in the same core half may lie in the same axial plane.

2.

Detectors in the same plane shall have quarter core radial symmetry.

c.

For QUADRANT POWER TILT measurements with the Symmetric Incore Detector System at least 75% of the detectors in each core quadrant shall be OPERABLE.

APPLICABILITY: When the incore detection system is used for surveillance of:

a.

The AXIAL POWER IMBALANCE, cr b.

'The QUADRANT POWER TILT.

ACTION:

With less than the specified minimum incore detector arrangement OPERABLE, do not use.incore detector measurements to determine AXIAL POWER IMSALA!CE or QUADRANT F0WER TILT. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l CRYSTAL RIVER - UNIT 3 3/4 3-26 l

i r

4

~

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (seconds) 9.

(Continued)

MUV-163 check #

open during HPI and NA MUV-25 #

iso. dur. nor, operation 60 MUV-164 check #

NA MUV-26 #

NA 60 MUV-160 check #

open during HPI and MUV-23 #

iso. dur. nor. operation 60 MUV-161 check #

open during HPI and NA MUV-24 #

iso dur. nor, operation 60 MUV-27 #

open dur. nor. operation 60 and closed during HPI 10.

SWV-39 #

iso. NSCCC from AHF-lC 60 SWV-45 #

60 SWV-35 #

iso. NSCCC from AHF-1A 60 SWV-41 #

60 SWV-37 #

iso. NSCCC from AHF-1B 60 SWV-43 #

60 SWV-48 #

to isolate NSCCC from 60 SWV-47 !

MUHE-1 A & 18 and WDT-5 60 SWV-49 #

60 SWV-50 #

60 SWV-80 #

iso. NSCCC from RCP-1A 60 SWV-84 #

60 SWV-82 #

iso. NSCCC fro *m RCP-1C 60 SWV-86 #

60 SWV-81 #

iso. NSCCC from RCP-10 60 SWV-85 #

60 SWV-79 #

iso. NSCCC from RCP-1B 60 SWV-83 #

60 SWV-1094 NSCCC to DRR'D-1 60 SWV-110#

60 CRYSTAL RIVER - UNIT 3 3/4 6-19 Amendment No. 11

i

~

TABLE 3.6-1 (Continued) l CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (seconds)

11. WDV-4 iso. WDT-4 from RB sump 60 WDV-3 60 WDV-60 & 61 iso. WDT-4 from WDT-5 60 WDV-94 & 62 iso. WDT-4 from WDP-8 60

. WDV-406 iso. gas waste disposal 60 WDV-405 from vents in RC system 60

12. WSV-3 iso. containment monitoring 60 WSV-4 system from RB 60 WSV-5 60 WSV-6 60 B.

CONTAINMENT PURGE AND EXHAUST 1.

AHV-lc & 10 iso. pur. sup. system 60 AHV-1B & 1A iso. pur. exhaust system 60 -

C-MANUAL 1.

IAV-28 iso. IA from RB NA IAV-29 NA 2.

LRV-50 iso. leak rate test system NA LRV-36 from RB-NA LRV-51 iso. atmos. vent and RB NA LRV-35 & 47 purge exhaust system NA from RB LRV-49 iso. atmos. vent from RB NA LRV-38 & 52 NA LRV-45 iso. LR test panel from RB NA LRV-44 NA 3.

MSV-146#

iso. misc. waste storage NA tank'from RCSG-1B 4.

NGV-62 iso. NG system from NA NGV-81 #

steam generators NA flGV-82 iso. NG system from pzr.

NA CRYSTAL RIVER - UtlIT 3 3/4 6-20

~

TABLE 4.7-1 5)

STEAM LINE SAFETY VALVES VALVE NUMBER LIFT SETTING (1 1%) (psig)

ORIFICE SIZE (inches)-

E' STEAM GENERATOR 3A M

x' Main steam line Al Si MSV - 34 1050 4.51 5

q MSV - 38 1070 4.515 MSV - 43 1090 4.51 5 c,

MSV - 40 1100 3.750 Main steam line A2 MSV - 33 1050

4. 51 5 MSV - 37 1070

4. 51 5 MSV - 42 1090 4.515 u,);

MSV - 46 1100 4.515 l

[

STEAM GENERATOR 3B Main steam line B1 MSV - 35 1050 4.515 MSV - 39 1070 4.51 5 MSV - 44 1090 4.51 5 MSV.- 47 1100 4.515 4

i Main steam line B2 MSV - 36 1050 4.515 MSV - 41 1070 4.515 MSV - 45 1090 4.515 MSV - 48 1100 3.750 9

i~

PLANT SYSTEMS EMERGENCY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 Two independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABLE with:

a.

One emergency feedwater pump capable of being powered from an OPERABLE emergency bus, and b.

One emergency feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one e-

. y feedwater system inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each emergency feedwater system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that the steam turbine driven pump develops a l

discharge pressure of > 1100 psig on recirculation ficw when the secondary steam supply pressure is greater than I

200 psig.*

When not in MODES 1, 2, or 3, surveillance shall be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering MODE 3 and prior to entering MODE 2.

l CRYSTAL RIVER - UNIT 3 3/4 7-4 Amendment No.11 I

s PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

Verifying)that each valve (manual, power operated or 2.

automatic in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

b.

At least once per 18 months, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on an emergency feed-water actuation test signal.

2.

Verifying that the steam turbine driven pump starts l

automatically upon receipt of an emergency feedwater actuation test signal.

3.

Verifying that the operating air accumulators for FWV-39 and FWV-40 maintain > 27 psig for at least one hour when isolated from their air supply.

1 CRYSTAL RIVER - UNIT 3 3/4 7-5 Amendment No. 11

PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank (CST) shall be O'PERABLE with a minimum contained volume of 150,000 gallons of water.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:.

With the condensate storage tank inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a.

Restore the CST to OPERABLE status or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or b.

Demonstrate the OPERABILITY of the condenser hotwell as a backup supply to the emergency feedwater system and restore the condensate storage tank to OPERABLE. status within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the contained water volume to be within its limits when the tank is the supply source for the emergency feedwater pumps.

4.7.1.3.2 The condenser hotwell shall be demonstr.ited OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying a minimum contained volume of 150,000 gallons of water whenever the condenser hotwell is the supply source for the emergency feedwater system.

CRYSTAL RIVER - UNIT 3 3/4 7-6

.-

ML19317G521

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