Text

Forwards Addl Changes to Be Incorporated Into Tech Specs Prior to Certification
	ML20210A711
Person / Time
Site:	Seabrook
Issue date:	09/12/1986
From:	Devincentis J; PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Novak T; Office of Nuclear Reactor Regulation
References
	SBN-1192, NUDOCS 8609170315
	Download: ML20210A711 (14)
	v • d • e

_ _. _.

September 12, 1986 SBN-1192 T.F. B7.1.2 United Ststes Nuclear.Rogulatory Commission Washington, DC 20555 Attention:

Mr. Thomas M. Novak, Acting Director Division of PWR Licensing-A Kef e rence :

(a) Construction Permits CPPR 135 and CPPR-136, Docket No.'s 50-443 and 50-444.

Subj ect: Additional Comments on Seabrook Station Technical Specifications.

Dear Sir:

As a result of our continuing ef fort to assure the accuracy of the final Technical Specifications for See. brook Station, we have identified several additional changes that must be incorporated into the Seabrook Station Technical Specifications prior to certification. Enclosure I to this letter provides marked up copies of the Seabrook Station Final Draf t Technical Specifications which reflect our comments. Upon inclusion of these comments into the Seabrook Station Technical Specifications and our verification of this inclusion, certification of the Technical Specifications will be possible.

It is our desire to certify the technical specifications as soon as possible. Should you or your staff have any questions concerning these comments, please contact Mr. Warren Hall at (603) 474-9574 extension 4046.

Very truly yours, v/

s J. DeVincentis Director of Engineering Enclosure cc: ASLB Service List 860/170315 860912 PDR ADOCK 05000443 A

PDR hoO\\

P.O. Box 300. Socbrook NH 03874 Tetephone(603)474-9521 l19l

TABLE 3.3-4 (Continued)

TABLE NOTATIONS

Time constants utilized in the lead-lag controller for Steam Line Pressure-Low 1 > 50 seconds and 12 < 5 seconds.

CHANNEL CALIBRATION shall ensure are t that these time constants are adjusted to these values.

"*The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate-High is less than or equal to 50 seconds.

CHANNEL CALIBRATION shall ensure that this Time constant is adjusted to this value.

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I SEABROOK - UNIT 1 3/4 3-29

r TABLE 4.3-6 (Continued) g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8

O 7

CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE cz INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED m

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CASE 0VS WASTE PROCESSING SYSTEM (Providing Alarm and Automatic Termination of Release)

a. Noble Gas Activity Monitor D

N.A.

R(6)

Q(1) 4.

TURBINE. GLAND SEAL CONDENSER EXHAUST -;

a. Iodine Samp1er

)(sN4 N. A.

N.A.

N.A

b. Particulate Sampler

,W $

N.A.

c. Sampler Flow Rate Indicator D

N.A.

5.

RADI0 ACTIVE GAS WASTE SYSTEM CUBICLE EXPLOSIVE GAS MONITORING SYSTEM

a. Hydrogen Monitors D

N.A.

Q(4)

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TABLE 4.3-6

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RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8

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CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE E

INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED Z

w 1.

RADI0 ACTIVE GAS WASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM 0xygen Monitor D

N.A.

Q(5)

M j

(Process) 2.

PLANT VENT-WIDE RANGE GAS MONITOR

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

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b. Iodine Sampler YJA N.A.

N.A.

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c. Particulate Sampler XNed N.A.

N.A.

d. Flow Rate Monitor 0

N.A.

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e. Sampler Flow Rate Monitor D

N.A.

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FINAL MT V EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T,y GREATER THAN OR EQUAL TO 350*F SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that the following valves a.

are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position SI-V-3 Accumulator Isolation Open g S

-f SI-V-17 Accumulator Isolation Open +

SI-V-32 Accumulator Isolation Openz +- 2 SI-V-47 Accumulator Isolation Ope SI-V-114 SI. Pump to Cold-Leg Isolation Open RH-V-14 RHR Pump to Cold-Leg Isolation Open RH-V-26 RHR Pump to Cold-Leg Isolation Open RH-V-32 RHR to Hot-Leg Isolation Closed RH-V-70 RHR to Hot-Leg Isolation Closed SI-V-77 SI to Hot-leg Isolation Closed SI-V-102 SI to Hot-Leg Isolation Closed b.

At least once per 31 days by:

1)

Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and i.

2)

Verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

By a visual inspection which verifies that no loose debris (rags, c.

trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1)

For all accessible areas of the containment prior to establish-ing PRIMARY CONTAINMENT INTEGRITY, and 2)

Of the areas affected within containment at the completion of each containment entry when PRIMARY CONTAINMENT INTEGRITY is

$t 1ished.

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m-u" SEABROOK - UNIT 1 3/4 5-5

PLANT SYSTEMS TURBINE CYCLE ATHOSPHERIC RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 The atmospheric relief valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.*

ACTION:

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SURVEILLANCE RE'QUIREMENTS 4.7.1.6 Each atmospheric relief valve shall be demonstrated OPERABLE:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that the nitrogen accumulator tank is at a pressure greater than or equal to 500 psig.

b.

Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, verify that all valves will open and close fully.

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When steam generators are being used for decay heat removal.

SEABROOK - UNIT 1 3/4 7-10

b5b ud PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK

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LIMITING CONDITION FOR OPERATION 3.7.5 The ultimate heat sink (UHS) shall be OPERABLE with: ~

a.

A service watar cumphouse water level at or* above C-

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b.

A mechanical draft cooling tower comprised of one cooling er ce I with one OPERABLE fan and a second cell with two OPERABLE an;_ and

.2,/f a contained basin water level of equal to or greater th 3m W* feet a bulk average water temperature of less than or equa to 67.3*F a

A portable tower makeup pump system stored to be OPERABLE for 30 days c.

following a Safe Shutdown Earthquake.

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

' ACTION:

With the service water pumphouse inoperable, restore the service a.

water pumphouse to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in 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 .

b.

With the mechanical draft cooling tower inoperable, restore the cooliotj tower to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in 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 .

With the po'rtable tower makeup pump system inoperable, continue c.

operation and notify the NRC within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in accordance with the procedure of 10 CFR 50.72 of actions or contingencies to ensure an adequate supply of makeup water to the mechanical draft cooling tower for a. minimum of 30 days.

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i ith e cooling tower in operation with valves aligned for tunnel heat treat-c _mant t a tower basin level shall be maintained at greater than or equal to L

q(44.65. ~ j,eep and the bulk average temperature shall be maintained at,le equal to 71*F.

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SEABROOK - UNIT 1 3/4 7-14 1

JUN 2 51985 n -

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"d PLANT-SYSTEMS ULTIMATE HEAT _ SINK SURVEILLANCE REQUIREMENTS 4.7.5 The ultimate heat sink shall be determined OPERARLE:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by:

w 1)

Verifying th water level in the s.ervice wa pumphouse to be at or above k'-9 */

J 2)

Verifying the wo%Wanical drafy15b g tower basin to bie greater than or equal to a level o JSP? fec.

n.sS ~

b.

At least once per week by verifying th3t the w te the cechanical draft cooling tower basin to be at a bulk average temperature of 67.3*F.

c.

At least once per 31 days by:

1)

Starting from the control room each UH3 cooling towar fan that is required to bc OPERABLE and operating each of those fans for at least 15 r.inutes, and 2)

Verifying that the portable tower makeup pump systen is stored in its design operational readiness state.

d.

At least once per 18 months bf verifying automatic actuation of eacti cooling tower fan on A Tower Actuation test signal.

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SEABROOK - UNIT 1 3/4 7-15 JijN 2 51885 l

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PLANT SYSTEMS 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM Emh LIMITING CONDITION FOR OPERATION 3.7.6 Two independent Control Room Area Ventilation Systems shall be OPERABLE.

APPLICA8ILITY: All MODES.

ACTION:

c MODES 1, 2, 3, and 4:

L With one Control Room Area Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in, 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 .

MODES 5 and 6:

With one Control Room Area Ventilation System inoperable, restore a.

the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE Control Room Area Ventilatien System in the recirculation mode, b.

With both Control Room Area Ventilation Systems inoperable, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

-SURVEILLANCE REQUIREMENTS

' ~ '

4.7.6 Each Control Room Area Ventilation System shall be demonstrated OPERABLE:

i At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the Control Room Area a.

Ventilation System is maintaining the temperature of equipment and instrumentation in the control room area below its limiting equipment qualification temperature.

b.

At least once per 1B x nths or after any significant modification to the Control Re2 /.ree entil. ion Systems by verifying a system flow rate of 25,70) f im y M t rougtr-the air conditioner unit (3A and 38) andaflowratep[ionunifWithadischar abahape6 d Abade ma up from each intake to the emergency filtr t of 2000 cfm 210% from the filtration it.

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ELECTRfCAL POWER SYSTEMS gl L

A.C. SOURCES OPERATING SURVEILLANCE REQUIREMENTS 4.8.1.1.2 (Continued) a)

Verifying deenergization of the emergency busses and load shedding from the emergency buss Q e4 oKsik I' wer b)

Verifying the diesel starts on t aseend spt signal, energizes the emergency busses wit 6er==tly t ed loads within 12 seconds, energizes tle auto-connected shutdown loads through the emergency power sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After ener-gization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 1 420 volts and 60 1 1.2 Hz during this test.

5)

Verifying that on an SI actuation test signal, without loss-of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes.

The generator voltage and frequency shall be 4160 420 volts and 60 1.2 Hz within 10 seconds after the auto-start signal; the steady-state generator voltage and frequency shall be maintained within these limits during this test;

.6)

Simulating a loss-of-offsite power in conjunction with an SI

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actuation test signal, and tower actuation test signal (TA);

and a)

Verifying en r '

tion of the emergency busses and load sheddin e

ergency busses; b)

Verifyi th dies starts on the auto-start signal, energi s th merg ncy busses with permanently connected nds, energizes the auto-connected loads ithin se emergenc (accide loads through the emergency power erates for greater than or equal to sequencer an 5 minutes while its generator is loaded with the emergency loads.

After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 420 volts and 60 1.2 Hz during this test; and Verifying that all automatic diesel generator trips,

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c) except engine overspeed, low lube oil pressure, 4160-volt bus fault, and generator differential, are automatically bypassed 'upon loss of voltage on the emergency, bus concur-rent with a Safety Injection actuation signal SEABROOK - UNIT 1 3/4 8-6 JUN 2 5 $86

REFUELING OPERATIONS 3/4.9.'6 REFUELING MACHINE

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LIMITING CONDITION FOR OPERATION 3.9.6 The refueling machine and auxiliary hoist shall be used for movement of drive rods or fuel assemblies and shall be OPERABLE with:

a.

The refueling machine used for movement of fuel assemblies having:

1)

A minimum capacity of 4000 pounds, and 2)

An overload cutoff limit less than or equal to 3900 pounds.

b.

The auxiliary hoist used fo ing and unlatching drive rods having:

AlCO 1)

A minimum capacity f 3000 pou ds, and 2)

A load indicator which shall be used to prevent lifting loads in excess of 1000 pounds.

APPLICABILITY:

During movement of drive rods or fuel assemblies within the reactor vessel.

ACTION:

With the requirements for refueling machine and/or hoist OPERABILITY not satis-fied, suspend use of any inoperable refueling machine and/or auxiliary hoist from operations involving the movement of drive rods and fuel assemblies within the reactor vessel.

SURVEILLANCE REQUIREMENTS 4.9.6.1 The refueling machine used-for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of such operations by performing a load test of at least 4000 pounds and demonstrating an automatic load cutoff when the refueling machine load exceeds 3900 pounds.

4.9.6.2 The auxiliary hoist and associated load indicator used for movement of drive rods within the reactor vessel shall be demonstrated OPERABLE within 100 hou f o the start of such operations by performing a load test of at least Seet pou ds.

k SEABROOK - UNIT 1 3/4 9-6

REFUELING OPERATIONS FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM SURVEILLANCE REQUIREMENTS 4.9.12b (Continued) 1)

Verifying that t.he cleanup system satisfies the in place penetration a

, bypass leakage testing acceptance criteria of less than'.

and uses the test procedure guidance in Regulatory Positions C.5.a, C.S.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978,* and the system flow rate is ~& cfm i 10%;

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2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,* meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52. Revision 2, March 1978, by showing a methyl iodide penetration of less than 1.0% when tested at a temperature of D 8C at a relative hu-midity of 70% in accordance wi);fFA3TM-03803; an 1 /J M O

/0 3)

Verifying a system flow rate c f 1MERIE cfm i M% d ing system operation when tested in acconQnce with ANSIM1980.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying, c.

within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,*

meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978,* by showing a methyl iodide penetration of less than 1.0% when tested at a tem-perature of 30 C and at a relative humidity of 95% in accordance with ASTH-D3803.

d.

At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches e while operating the system at a flow rate of er e cf i 10%,

2) ng that the system maintains the spent fuel storage pool area at a negative pressure of greater than or equal to 1/4 inch Water Gauge relative to the outside atmosphere during system operation,

ANSI N510-1980 shall be used in place of ANSI H510-1975 as referenced in Regulatory Guide 1.52, Rev. 2, March 1978.

SEABROOK - UNIT 1 3/4 9-14

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rn#1IEri REFUELING OPERATIONS FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM g

SURVEILLANCE REQUIREMENTS 4.9.12d (Continued) 3)

Verifying that the filter cross connect valve can be manually a

opened, and Verifying that the heaters dissipate 95 2 11 kW when tested in i

4) accordance with ANSI H510-1980.

After each complete or partial replacement of a HEPA filter bank, by enetratio e.

verifying that the cleanup system satisfies the in-plac accordance leakage testing acceptance criteria of less than for a DOP test aerosol while operating the system with ANSI N510-1980 at a. flow rate of cfm i 10%.

After each complete or partial replacement of a charcoal adsorber f.

bank, by verifying that the cleanup system satisfies the in plac penetration leakage testing acceptance criteria of less than.

in accordance with ANSI N510-1980 for a halogenated hydrocarbon re-frigerant test gas while' operating the system at a flow rate of W cfm i 10%.

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3/4 9-15 SEABROOK - UNIT 1

U me a RADI0 ACTIVE EFFLUENTS GASEOUS EFFLUEhTS GAS STORAGE TANKS l

. LTMTTTun t'nunTTinw3nR OPERATION __.. _.

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3.11.2.

e quantity of radioactivity contained in the hydrogen purge tydr.

ihall be li d to less than or equal o 198,000 Curies of noble gase M con-idered as Xeno 3 equivalent).

A 'PLICABILITY: At al es.

AlTION:

a.

With the quantity of ra etive material in the hydrogen purge tant exceeding the above limit, gMitately suspend all additions of ra within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank

co'dioactive matex.i.al to the#

ntents to within the Lidh 7n cribe-the-events -leadisj-to-thisconditioninthpgextf emiannua ioactive Effluent Release Report pursuant todpecific. tion 6.8.1..

b.

Theprovisip Specifica. ions 3.0.3 and 3.0.

not applicabl.

iURVEILLANCE IREMENTS 4.11.

The quantity of radioactive, material contained in each gas stora

/1ours when radioaggtgalsgjeJei g;4dded.itoethouterik***geg[,j tan all be determined to be withinithe above limit at least once E

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4 SEP 8 1986 l'

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,x In Reply l Refer'To:

,' Docket:.i50-298/86-01, 3

Nebraska Public Power District ATTN:

J. M.'Pilant, Manager, Technical Staff-Nuclear Power Group P. O. Box 499 Columbus, Nebraska-~68601 Centlemen:

This refers to the inspection conducted by Mr. J. R. Boardman of this office

-and-two consultants during the period January 6-10, 1986, of activities authorized by NRC Operating License DPR-46 for the Cooper Nuclear Station.

Our letter, dated March 14, 1986, forwarded the results of this inspection.

As a result of this inspection, an enforcement conference was held in the Region IV offices on March 26, 1986.

After due consideration of the matters discussed at the enforcement conference and the aforementioned inspection report, we have concluded that certain activities conducted under your license were in violation of NRC requirements. Consequently, you are required to respond to this violation in writing, in accordance with the previsions of Section 2.201 of the NRC's

" Rules of Practice," Part 2, Title 10, Code of Federal Regulations. Your response should be based on the specifica contained in the enclosed Notice of Violation.

The response directed by this letter and the accompanying Notice of Violation is not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

Should you have any questions, we shall be pleased to discuss them with you.

Sincerely.

Oiiginal Signed By J. E. Gagilardo J. E. Gagliardo, Chief Reactor Projects Branch

Enclosure:

As stated cc:

If See n page RIV:Pb RPB JPJaudentje JECag a do 9/k /86 9/ '

4tD 6

8609170310 860908

% L PDR ADOCK 05000298 G

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ccwIanc1:

Guy Horn, Division Manager of Nuclear Operations Cooper Nuclear Station, P. O. Box 98 Brownville, Nebraska 68321 Kansas Radiation Control Program Director Nebraska Radiation Control Program Director bec to DMB'(IE01)

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bec distrib.;by RIV:

RPB DRSP

Resident-Inspector R. D. Martin, RA

Section Chief (RPB/A)

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ML20210A711

Text

Dear Sir:

Enclosure:

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