ML19224C704

Forwards Replacement Pages Which Correct Errors in Amends 57 & 58 to License DPR-3

ML19224C704
Person / Time
Site:	Yankee Rowe
Issue date:	05/09/1979
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	Groce R YANKEE ATOMIC ELECTRIC CO.
References
NUDOCS 7907060072
Download: ML19224C704 (10)

Text

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UNITED STATES NUCLE AR REGULATORY COMMISSION

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May 9,1979

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Docket No. 50-29 Mr. Robert 11. Groce Licensing Engineer Yankee Atomic Electric Ccmpany 20 Turnpike Road Westboro, Massachusetts 01531

Dear Mr. Groce:

Enclosed is a replacement page 3/4 9-8 which corrects an error that occurred inadvertently during the issua ace of Amendment No. 57 to License No. DPR-3 dated April 3, 1979, for Yankee-Rowe.

In addition, we are enclosing the following replacement pages for the purcose of correcting Anendment No. 53, dated April 3,1979:

3/4 3-17, 3/4 3-18, 3/4 3-19, 3/4 3-20, 3/4 4-3, 3/4 4-4, 3/4 4-7 and 3/4 4-8.

We regret any inconvenience caused by these administrative errors.

Sincerely,

'f'w.1 We -

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,f DennisL.Ziemann,$)11ef Operating Reactors Branch $2 Division of Operating Reactors

Enclosures:

As stated cc w/ enclosures:

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REFUELING OPERATION _S_

SHIELD TANK CAVITY MANIPULATOR CRANE OPERABILITY LIMITING CCNDITION FOR OPERATION Control rods -nd fuel assen blies shall be handled one-by-one 3.9.6 with an OPERABLE shield tank cavity manipulator crane and universal handling tool with:

J A minimum capacity of 900 pounds, and a.

l An overload cut off limit < 4800 pounds.

t,.

During movement of control rods or fuel assemblics APPLICABILITY:

within the reactor pressure vessel.

ACTION:

With the requirements for crane and handling tool OPERABILITY not satisfied, suspend use of the inoperable manipulator crane or handling tool f5om cperations involving the movement of control rods and fuel assemblies within the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTE The manipulator crane and handling tool used for movement of 4.9.6 control rods or fuel asserblies within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 900 pounds, demon-strating an automatic load cut off when the crane load exceeds 4800 l

pounds, and verifying proper operation of the handling tool, YANKEE-ROWE 3/4 9-7 Amendment No. 33, 58

• ApA REFU.ELING OPERATIONS CRAN E T PA, E L - SP E 'iT F UE L P I T LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 900 vounds shall be prohibited from travel over the spent fuel pit except io-the:

a.

Spent fuel pit building roof hatches, b.

Spent fuel inspection stand, c.

Fuel handling eauipment, d.

Spent fuel racks, e

Temporary ga te, and f.

5hielding panels APPLICABILITY: With fuel assemblies in the spent fuel pit.

ACTION:

Witn the requirements of the above specification not satisfied, place the crane load in a safe condition.

The provisions of Specification 3.0.3 are not applicable.

SUR'/E ILLANCE REQUIREMEF,TS 4.9.7 Loads in excess of 900 pounds shall be prevented from traveling over the spent fuel pit by administrative control except that the:

Spent fuel pit building roof hatches, the spent fuel inspection stand, a.

the fuel handling equipment, spent fuel racks, the temporary gate and the shielding panels may travel over the spent fuel pit in accordance with approved wri tten procedures.

b.

Spent f uel storage racks, the spent fuel inspec tion s tand, the temporary qate and the shi'lding panels shall be prevented from traveling over fuel assenblies in the spent fuel pit by administrative control', and Fuel handling equip.ent when moved for maintenance shall be prevented c.

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travelir,9 v.er tuel asser.blies in the spent fuel pit by aa ' in : s tra ive c en' ntl.

Y AM 7 E - F :..T 3/4 9.E Amenda.ent No. 39, SJ, 57

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A INSTRL' MENT ATION 3/4.3.3 t10NITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATI0r!

3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-4 shall be OPERABLE with their alarm setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-4.

ACTION:

a.

With a radiation monitering channel alarm setpoint exceeding the Alarm Setnoint show., in Table 3.3-4, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take thc ACTION shown in Table 3.3-4.

c.

lhe provisions of Speci'ications 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.3.3.1 Eac, radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of tne CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operaticas during the OPERATIONAL MODES and at the frequencies shown in Table 4.3-3.

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1 TABLE 3.s-4 RADIATION MONITORING INSTRUMENTATION E

A m

MINIMUM h

CHANNELS APPLICABLE ALARM MEASUREMENT INSTRUMENT _

OPERABLE MODES SETPOINT RANGE ACTION

c t

1.

AREA MONITORS 1)

Fuel Manipulator 1

1 5 mr/hr or 2 x 0,5 - 50 mr 11 l

a.

Spent Fuel Pit Area background, which-Gamma Guard ever is greater b.

Containment

<10 mr/hr or 2 x C - 1000 mr 12 l

1)

Fuel Manipulator 1

m Eackground,which-2 Ganina Guard ever is greater m,

E 2.

PROCESS MONITORS 6

1)

Main Coolant System 1 1,2, 3, & 4 NA 10 - 10 cpm 13 a.

Containment g

Leakage Air Par-in E

ticulate Monitor a

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b.

Radioactive Gaseous Waste Monitor

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Primary Vent Stack Monitor 6

Monitor 1

At all times 1900 cpm greater 10 - 10 cpm 14 a)

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h TABLE 3.3-4 (Continued)

TABLE NOTATION When handling irradiated fuel, control rods, or sources.

l (1)

Per steam generator in a non-isolated loop.

ACTIC,. P ATEMENTS With the number of channels OPERABLE less than required l ACTION 11 -

by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

WiththenumberofchannelsOPERABLElessthanrequiredl ACTION 12 -

by the Minimum Channels OPERABLE requirement, suspend all operations involving CORE ALTERATIONS.

With the number of channels OPERABLE lo.s than required l ACTION 13 -

by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1.

With the number of channels OPERABLE less than required ACTION 14 -

by the Minimum Channels OPERABLE requirement, suspend all planned releases and releases from the evaporator to the atmosphere through the primary vent stack.

With the number of channels OPERABLE less than required ACTION 15 -

by the Minimum Channels OPERABLE requirement, provide an OPERABLE temporary continuous monitor within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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VANKEE-ROWE 3/4 3-20 Amendment No. 58

MAIN COOLANT SYSTEM ISOLATED LOOP LIMITING CONDITION FOR OPERATION 3.4.1.2 The boron concentration of an isolated loop shall be maintained greater than or equal to the boron concentration of the operating loops.

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

With the requirements of the above specification not satisfied, do not open the isolated loop's stop valves; either increase the boron concen-tration of the isolated loop to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 /> with the unisolated portion of the Main Coolant System borated to a SHUIDOWN MARGIN (all rods inserted) equivalent to at least 5% ak/k at 200"F.

SURVEILLANCE REQUIREMENTS 4.4.1.2.1 The boron concentration of an isolated loop shall be determined to be greater than or equal to the boron concentration of the operating loops at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

With Main Coolant System loop isolation valve controls removed from service and mechanically prevented from operation by lock and key, the frequency of determination that the boron concentration of the isolated loop is greater than or equal to the boron concentration of the operating loops may be reduced to 3 times per week with a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between analyses.

4.4.1.2.2 An isolated loop shall be determined to be borated to at least 5% AK/K at 200 F before loop temperature is retJced > 30 F below Rith Main the highest cold leg temperature of the operating loops.

Coolant System loop isolation valve controls, main steam line isolation valves and main coolant pump controls removed from service and mechanically prevented from operation by lock and key, the boron concentration of the isolated loop may be reduced to that existing in the Main Coolant System at that time.

[' O '

(1. 3 YANKEE-ROWE 3/4 4-3

MAIN COOLANT SYSTEM ISOLATED LOOP STARTUP LIMITING CONDITION FOR OPERATION 3.4.1.3 A main coolant loop shall remain isolated until:

a.

The temperature of the cold leg of the isolated loop is within 30 F of the highest cold leg temperature of the operating loops.

b.

The boron concentration of the isolated loop is not less than the main coolant system boron concentration, and c.

The reactor is subcritical by at least 1 percent ak/k APPLICABILITY: All MODES.

ACTION:

With the requirements of the above specification not satisfied, suspend startup of the isolated loop.

SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The isolated loop cold leg temperature shall be determined to be within 30*F of the highest cold leg temperature of the operating l

loops within 30 minutes prior to opening the cold leg stop valve.

4.4.1.3.2 The isolated loop baron concentration shall be determined to be not less than the Main Coolant System boron concentration within i hours prior to opening the cold leg stop valve.

4.4.1.3.3 The reactor shall be determined to be subcritical by at least 1 percent ak/k within 30 minutes prior to opening the cold leg stop valve.

O-(), *

(ANKEE-ROWE 3/4 4-4 Amendment No. (9, 58

MAIN COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with a steam bubble.

APPLIC ABI' ITY :

MODES 1 and 2 ACTION:

With the pre;surizer inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.4 No other requirements other than those specified in accordance with 10 CFR 50.55a(g).

oo-g, YANKEE-ROWE 3/4 4-7 Amendment No. 49, 50

MAIN COOLANT SYSTEM I 3/4.4.5 MAIN COOLANT SYSTEM LEAKAGE LEAKAGE DETEj O N SYSTEM _S_

LIMITING CONDITION FOR OPERATION The following Main Coolant System leakage detection systems 3.4.5.1 shall be OPERABLE:

At least one containment atmosphere particulate radioactivity l

a.

monitoring system, The containment drain tank level monitoring system.

b.

The incore detection system thimble leak alarm system.

c.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the above required radioactivity monitoring leakage detection system inoperable, operation may continue for up to 7 days provided:

a.

Main Coolant System water inventory balance is performed at 1.

least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The other above required leakage detection systems are OPERABLE, 2.

and Appropriate grab samples are obtained and analyzed at least 3.

once per hour:

otherwise, 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 />.

With the containment drain tank level monitoring system inoperable, restore the inoperable system to OPERABLE status within 7 days or b.

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 />.

With the incore detection system thimble leak alarm system inoper-able, restore the leak alarm system to OPERABLE status within 7 days c.

or close all thimble isolation valves; restore the leak alarm system to OPERABLE status within 31 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 th following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

"n' 0;

YANKEE-ROWE 3/4 4.B Amendment No. 58

._