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Forwards Attachments to Util 801110 Response to NRC Re TMI-2 Lessons Learned Category a Items.Attachments Were Omitted Due to Administrative Error
	ML19345B961
Person / Time
Site:	Calvert Cliffs
Issue date:	11/25/1980
From:	Ash R; BALTIMORE GAS & ELECTRIC CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8012030248
	Download: ML19345B961 (12)
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B ALTIMORE -

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OAS AND j

og ELECTRIC N-N CHARLES CENTER. P.O. BOX 1475 BALTIMORE. MARYLAND 21203

. ELECTRIC ENGINEERING

. DEPARTMENT.

?'cVer.ber ?5, 1980 "r.. Harold R. Denton Office of ?!uclear Peactor Regulation U. S. !!uelear Reculatory Conmission

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References:

(2 ) NEC ' letter dated 7/12/90 fron D. 'J.

"isenhut to all pressurir.ed vster reactor licenseos.

(2) P1&E letter dated 11/10/30 frcr A. E. I.undvall, Jr.,

to U. F. Centon.

Dear ?'r. Denton:

.Due.to.an adminictrative error, the attachr.cnts to the referenced i

letter (?) were not sent out. Please find enclosed forty (LO) conies of thece attach entc.

Ver.* truly yours, i

t R. F. Ach Chief Nuclear Engineer IFA/smn Enclosur2s cc:

J. A. Biddison, Esquire G. F. Trowbridge, Esquire Messrs. E. I..

Conner, Jr. - NRC

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TABLE 4.3-10 l

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQU l

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CHANNEL m

CHANNEL CALIBRATION E

CHECK _

INSTRUMENT _

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Power Range Nuclear Flux R

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Containment Pressure

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Reactor Coolant Outlet Temperature

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Reactor Coolant Total Flow R

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~ Pressurizer Pressure R

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Pressurizer Level R

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Steam Generator Pressure R

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Steam Generator Level N

10. Feedwater Flow N

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POST-ACCIDENT MONITORING INSTRUMENTATION c

Q MINIMUM n

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CHANNELS INSTRUMENT OPERAELE I'

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Power Range Nuclear Flux 2

m_

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Containment Pressure 2

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Wide Range Logarithmic Neutron Flux Monitor 2

4.

Reactor Coolantl0utlet Temperature 2

5.

Reactor Coolant' Total Flow 2

tap 6.

Pressurizer Pressure 2

7.

Pressurizer Level 2

8.

Steam Generator Pressure 2/ steam generator 9.

Steam Generator Level 2/ steam generator 10.

Feedwater Flow 2

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LIMITING CONDITION FOR OPERATION 5

E 3,4. l '3 j

2.".3 Two l

valves (shal] power operated relief valves (PORVs) and their associated block be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

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ACTION:

E E

a.

With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore 5

the PORV(s) to OPERABLE status or close the associated block valve (s) i and remove power from the block valve (s); otherwise, be in at least i

HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the

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following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

E b.

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either f

restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in g

at.least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.3.1 EachPORVshallbedemonstratedOPERABLE{

^t 'eaet ene: per 31 d:y: by perf: ::n : Of Cliff'"EL FUNCTIONAL 4EST, ey. 'uding v h e Oper:tien, and K

At least once per 18 months by performance of a CHANNEL CALIBRATION.

m 4.4.3.2 Each block valve shall be demonstrated OPERABLE at least once per 4 eye by operating the valve through ona complete cycle of full travel.

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'h: :::rgency pouer cu;?'y for th OP'!: 2nd b' 9 "S'"?? S demen:trated OPER^.BLE at 1:2 t en: per le month: by tr:nferr%; m:tive and control power frc; the no ;;l te th: :: rgency power supply 7:nd Operating the V:h:: threugh C0mplete cycle Of ful' travel

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- Emergency Power Supply Requirements for Pressurizer Relief and Block-Valves - NUREG-0578, Item 2.1.1.

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REACTOR COOLANT SYSTEM

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PRESSURIZER r

i; LIMITING CONDITION FOR OPERATION i

~3co 3.4.4 The pressurizer shall be OPERABLE with at least S W + kw of pressurizer heaters and a water level between 90 and "A/ G inches, tt APPLICABILITY:

MODES 1, 2, and 3 ACTION:

I i

L'ith the prc::uri:cr inoperable te te er iaoperable e'ergeacy powea Supply te the prc urizer hc;ter; cither rc tere the inoperable : cr W poucr cupply. ithi-72 hour; er be i at le :t "0T ST%'DSY ithi-the r.cxt 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ; cr.d ir, HOT SMLTDOEM withir the fcilew g 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With i

the pressurizer Other' ice inoperable, be in at least HOT STANDBY with the 2

reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in the HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS LE V E. L.

4.4.4.1 The pressurizer water '; !" r shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

A 4.4.4.)( The emergoncy power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by tranferring power from the normal to the emergency power supply and energizing the heaters.

LL/

- Emergency Power Supply Requirements for Pressurizer Heaters - NUREG-0578, Item 2.1.1.

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Baltsmere Gas and Electrse Company

ADMfNISTRAT7VE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for com' parable positions, except for the Radiation Safety Engineer who shall meet or exceed the qualificati'ons of Regulatory Guide 1.8, September 1975y %.rwe. %,rTeew. m % 5,&

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6.4 TRAINING F* *

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6.4.1 A retraining _and replacement training program for the facility staff shall be maintained under the direction of the Ganaral Supervis'or -

Training and Technical Services and shall meet or sxceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintcined under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code -

1975.

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

FUNCTION 6.5.1.1 The POSRC shall fun tion to advise the Plant Superintendent on a

matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PDSRC shall be composed of the:

Chairman:

Plant Superintendent Member:

General Supervisor - Operations Member:

General Supervisor - Electrical and Controls Member:

General Supervisor - Chemistry Member:

Principal Engineer - Plant Engineering Nuclear Member:

General Foreman - Maintenance and Modifications Member:

Supervisor - Nuclear Fuel Management Member:

General Supervisor - R3diation Safety Member:

General Supervisor - Training and Technical Service.

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in POSRC activities at any one time.

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CALVERT CLIFFS UNIT 2 6-6 l_-. d...; c,t,'b. ;;,'

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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION!

Condition of Unit 2 - No Fuel in Unit 1 LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SOL 1

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NE Condition of Unit 2 - Unit 1 in MODES 1, 2, 3 or 4

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LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SOL **

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Condition of Unit 2 - Unit 1 in Modes 5 or 6 LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SOL **

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TABLE 6.2-1 (Continued)

Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE

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ALTERATIONS during fuel reloading.

- Assumes each ^ individual is licensed on each unit..

Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided imediate action is taken to restore the shif t crew composition to within the minimum requirements of Table 6.2.1.

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CALVER.T CLIFFS - UNIT 2 6-5 I

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'f INSTRUMENTATION 3ASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION 4

The_0PERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is_ consistent with the recommendations of Regulatory Guide 1.97, "Instru-mentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident", December 1975. % mgtu,. on y "Tmr-t Lesso~s twcs TAst r w~ec how s %v mg Euv-gm (tec-www.on s '.

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires _will reduce the potential for damage-to safety related equipment and is an integral eleme t in tne overall facility fire protection program.

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_In the event that a portion of the fire detect on instrumentation i

is inoperable, the establishment of frequent fire patrols in the-affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

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CALVERT CLIFFS - UNIT 2 B 3/4 3-3

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The requirement that 13ejkw of pressurizer heaters and their associated l

controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a less of offsite power condition to maintain natural circulation at HOT STANDBY.

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([ct ocF VM vp The power operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves.

These relief valves should a relief valve become inoperable.have remotely operated block The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency power source to ensure the ability to seal this possible RCS leakage path.

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r-LICENSE CONDITIONS FOR NUREG-0578 TMI-2 LESSGNS LEARNED CATEGORY "A" ITlMS System Integrity The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program shall include the following:

1.

Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.

Leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

Iodine Monitoring The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

1 l

ML19345B961

Text

References:

Dear ?'r. Denton:

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