ML19257C292

Revised Pages 6-20,7-73,6-6,7-31,7-32,7-58,7-55,7-31 & 7-45 to Tech Specs Re Visual Insp of Critical Hose Stations, Snubbers,Auxiliary Feedwater Sys & Typographical Error on NFPA Code Listing

ML19257C292
Person / Time
Site:	Calvert Cliffs
Issue date:	01/22/1980
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19257C290	List: ML19257C289 ML19257C292
References
NUDOCS 8001250528
Download: ML19257C292 (15)

Text

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d. Records of radiation exposure for all individuals entering radiation control areas. ,

e. Records of gaseous and liquid radioactive material released to the environs.

f. Records of transient or operational cycles for those facility components identified in Table 5.7-1.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

1. Records of Quality Assurance actiyities required by the QA Manual h FM4/,

J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

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k. Records of meetings of the POSRC and the OSSRC.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. ,

6.12 liIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "alam signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20:

a. A high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to anter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.

1809 336 0 CALVERT CLIFFS - UNIT 142. 6-20 AmendmentNo.%

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Cleury No. 2 fa79-13c fGy I c}. l l PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITIONS FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.

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APPLICABILITY: Whenever "equipme'ni in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7-5 inoperable, route an additional equivalent capacity fire hose to

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the unprotected area (s) from an OPERABLE hose station within I

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hour. .

,b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ,,

SURVEILLANCE REQUIREMENTS

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4.7.11.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERABLE:

At least once per 31 days by visual inspection of the station b' a .'

to assure all required equipment is at the station. Hoss srAvicus 1.CcATED tu WE CC4TALMMFvr SHAU. W VISUALW MSPECT1h cu CActf REVTDR.

b. A N eaN N e Ye E IS So E Y

, 1. Removing the hose for inspection and re-racking, and

2. Replacement of all degraded gaskets in couplings.

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c. At least once per 3 years by:

1. Partially opening each hose station valve to verify valve j OPERABILITY and no flow blockage. I

2. Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose , station or replacement with a new hose.

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ALVERT CLIFFS - UNIT if 2 3/4 7-73 Mendment No. K ,

.1809 337 _

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PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2.1 At least two steam turbine driven steen generator auxiliary feedwater pumps, associated flow paths, and actuation system instrumentation shall be OPERABLE.

3.7.l.Z,.2. At least two auxiliary feedwater actuation system instrumentation thannds shall be OPERABLE kJH g f6 /%;t3 p c, j APPLICABILITY: MODES 1, 2, and 3.

1. i O 1 % 3 s d 3.7- 6 ACTION:

A. With one auxiliary feedwater pump inoperable, restore at least tao auxiliary feedwater pumps to GPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B. With one actuation system instrument channel inoperable take the ACTION snown in Table 3.7-y. '

SURVEILLANCE REOUIREMENTS 4.7 .1. 2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a. At least once per 31 days by:

1. Verifying that the steam turbine driven pump develops a Total Dynamic Head of .12800 ft. on recirculation flow when the secondary steam supply pressure is greater than 800 psig.

2. Verifying that each valve (manual, power operated, or automatic) in the flow path is in its correct position. Whenever the pump discharge manual valve is shut (during periodic testing) a dedicated individual will be stationed at the valve. This operator will be.

- in communication with the Control Room. Upon completion of periodic testing the valve will be returned to its proper position and verified in its proper position by an independent operator check.

b. At least once per quarter verify the operability of remotely operated valves.

' 4.7.1.2.2 After a Cold Shutdown period of 14 days or greater, a flow test shall

. be performed to verify the flow path from #12 Condensate Storage Tank to both steam generators. I 1809 338

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TABLE 3.7-3 AUXILI ARY FEEDWATER ACTUATION SYSTEM INSTRUMENTATION T".IP VALUES TRIP VALUE ALLOWABLE VALUE FUNCTIONAL UNIT Not Applicable Not Applicable A. Manual B. Feedwater Flaw-Lew 15 % 15 90 TABLE 3.7.-+

AUXILIARY FEEDWATER ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIMES RESPONSE TIME IN SECONDS INITIATING SIGNAL & FUNCTION Not applicable A. Manual f B. Feedwater Flow-Lew (80-300 e

• e 1809 339 _

TABLE 9.7-5 AUXILIARY FEEDWATER ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL # OF CilANNELS CilANNELS APPLICABLE TO TRIP OPERABLE MODES ACTION FUNCTIONAL UNIT CHANNELS A. Manual 2 1 1 1i A*

2 1 1g A*

B. Feedwater Flow- 1 Low ,

• The provisions of Spe,cification 3.0.4 are not applicable

1. At power levels greater than 15%

ACTI0tl STATEMENT Action A With the number of OPERABLE channels one less than the total number of channels, restore the inoperable channel to OPERARLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least il0T STAtlDBY 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 SituTDOWil within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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Pcy 4 g f-SURVEILLANCE RE0VIREMENTS 4.7.1.2.3 Each auxiliary feedwater actuation instrumentation channel shall be demonstrated operable by the performance of the channel check, channel calibration, and channel functional test operations during the Modes and at the frequencies shown in T@le 4.7.1. .1.

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'1809 541 .

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TABLE 4.7.1 - 1 AUXILIARY FEEDWATER ACTUATION SYSTEM INSTRlNENTATION SilRVEILLAllCE REQUIREMENTS CilNINEL MODES IN WilICll CilANNEL CilANNEL FUNCTIONAL SURVEILLANCE IS EMERGENCY FEE 0 WATER CllECK CAllBRATION TEST REQUIRED a

Manual Initiation A. N/A N/A H 1 B. Feedwater Flow-Low N/A R H 1 0

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6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for ccmparable positions, except for the Radiation Safety and Chemistry Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility sta ff shall be maintained under the direction of the Chief Engineer rr and shall meet or exceed 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 F1.re Brigade shall be maintained under the direction of the Chief Engineer and shall meet or exceed the require-ments of Section 27 of the NFPA Code-% - i 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) ,

FUNCTION ,

6.5.1.1 The POSRC shall function to advise the Chief Engineer on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The POSRC shall be composed of the:

Chairman: Chief Engineer Member: Nuclear Plant Engineer - Operations Member: Nuclear Plant Engineer - Maintenance

, Member: Nuclear Engineer Member: Radiation Safety and Chemistry Engineer Member: Supervisor - Technical Support Member: Performance Engineer 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.

CALVERT CLIFFS - UNIT 1 cf.7 6-6 Amendment No.

1809 343 .

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