ML20197C197

Forwards Corrections to Final Draft Tech Specs Re Reactor Trip Sys Instrumentation Trip Setpoints & ESFAS

ML20197C197
Person / Time
Site:	Seabrook
Issue date:	10/30/1986
From:	George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Novak T Office of Nuclear Reactor Regulation
References
SBN-1222, NUDOCS 8611060003
Download: ML20197C197 (9)

Text

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George S. Thomas October 30, 1986 N2w Hampshire Yankee Division p, B 21 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Thomas M. Novak, Acting Director Division of PWR Licensing-A

References:

(a) Facility Operating License NPF-56, Docket No. 50-443 (b) USNRC Letter dated June 18, 1986, " Final Draft Technical Specifications for Seabrook Power Station, Unit 1,"

T. M. Novak to R. J. Harrison (c) USNRC Letter dated June 26, 1986, " Changes to Seabrook Station Draft Technical Specifications," T. M. Novak to R. J. Harrison (d) USNRC Letter dated October 10, 1986, " Changes to Seabrook Station Final Draft Technical Specifications," T. M. Novak to R. J. Harrison (e) USNRC Letter dated October 15, 1986, " Changes to Seabrook Station Final Draft Technical Specifications," T. M. Novak to R. J. Harrison (f) PSNH Letter (SBN-1216) dated October 16, 1986,

" Certification of Sea'orook Station Unit i Technical Specifications," G. S. Thomas to T. M. Novak (g) USNRC Letter dated October 17, 1986, " Issuance of Facility Operating License NPF Seabrook ,

Station, Unit No. 1," T. M. Novak to R. J. Harrison '

Subj ect: Changes to Seabrook Station Technical Specifications l l

Dear Sir:

Reference (f) provided New Hampshire Yankee's (NHY) certification that, contingent upon incorporation of specified changes, the Final Draft Technical  ;

Specifications as forwarded by References (b), (c), (d), and (e) are  !

cc patible with the as-built plant configuration, the Seabrook Station FSAR

t. augh Amendment 60, the NRC Staff's Safety Evaluation Report through Supplement 5, and other docketed correspondence with the Nuclear Regulatory'  !

Commission Staff.

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P.O. Box 300 . Seabrook, NH 03874 . Telephone (603) 474-9574

United States Nuclear Regulatory Commission October 30, 1986 Attention: Thomas M. Novak Page 2 Reference (g) forwarded, as Appendix "A" to License No. NPF-56, Technical Specifications which differ in several areas from those Final Draft Technical Specifications certified by Reference (f). Corrections to these Technical Specifications are provided as Enclosure 1 in the form of marked-up pages. It is requested that these changes be incorporated into the Seabrook Station Technical Specifications as appropriate in order that they may reflect the specifications forwarded by References (b) thru (e) and as certified by Reference (f).

Should you have any questions regarding this matter, please contact Mr.

Warren J. Hall, Regulatory Services Manager, at (603) 474-9574, extension 4046.

Very truly yours, George S. Thomas Enclosure cc: Atomic Safety Licensing Board Service List

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ENCLOSURE I TO SBN -1222

. 6 TABLE 2.2-1 (Continued)

M REACTOR TRIP SYSTEN INSTRUMENTATION TRIP SETPOINTS B SENSOR R TOTAL ERROR

, FUNCTIONAL UNIT ALLOWANCE (TA) Z, (S) TRIP SETPOINT ALLOWABLE VALUE E 11. Pressurizer Water Level - High 8.0 2.18 1.82 592% of instrument 593.8% of instrument Q span span g 12. Reactor Coolant Flow - Low 2.5 1.87 0.6 190% of loop 189.4% of loop design flow

• design flow

• 1 7. o %

13. Steam Generator Water 17.0 15.28 1.76 > M-65 of narrow >7.5.9% of narrow Level Low - Low range instrument range instrument span span

14. Undervoltage - Reactor 15.0 1.39 0 >10,200 volts >9,822 volts Coolant Pumps

15. Underfrequency - Reactor 2.9 0 0 155.5 Hz >55.3 Hz u Coolant Pumps Turbine Trip

16. *

a. Low Fluid Oil Pressure N.A. N.A. N.A. 2500 psig >450 psig

b. Turbine Stop Valve N.A. N.A. N.A. >1% open >1% open Closure

17. Safety Injection Input N.A. N.A. N.A. N. A. N.A.

from ESF

• Loop design flow = 95,700 gpm i

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TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS E

' SENSOR TOTAL ERROR i

E FUNCTIONAL UNIT ALLOWANCE (TA) Z_ (S) TRIP SETPOINT ALLOWABLE VALUE Z

g 1. Safety Injection (Reactor Trip, Feedwater Isolation, Start Diesel Generators, Phase "A" Isolation, Containment Ventilation Isolation, and Emergency Feedwater, Service Water to Secondary Component Cooling Water Isolation, CBA Emergency Fan / Filter Actuation, and Latching Relay).

g a. Nanual Initiation N.A. N.A. N.A. N.A. N.A.

87 b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

2 ..

c. Containment Pressure--Hi-1 4.2 0.71 1.67 1 4.3 psig. 1 5.3 psig

d. Pressurizer Pressure--Low 13.1 485c 10.71 1.69 3 4075 psig 1 1840 psig

e. Steam Line Pressure--Low 13.1 10.71 1.63 > 585 psig > 568 psig*

2. Containment Spray

a. Manual Initiation N.A. N.A. N. A. N.A. N.A.

b. Automatic Actuation Logic N.A. N.A. N. A. N.A. N.A.

and Actuation Relays

c. Containment Pressure--Hi-3 3. 0 0.71 1.67 5 18.0 psig 5 18.7 psig

PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5 The ultimate heat sink (VHS) shall be OPERA 8LE with:

a. A service water pumphouse water level at or above 5'-0",(einus 36'-0"MeanSeaLevel,USGSdatum,}and

b. A mechanical draft cooling tower comprised of one cooling tower cell with one OPERABLE fan and a second cell with two OPERABLE fans, and a contained basin water level of equal to or greater than 42.15" feet at a bulk average water temperature of less than or equal to 67.3*F, and

c. A portable tower makeup pump system stored to be OPERABLE for 30 days following a Safe Shutdown Earthquake.

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

ACTION:

a. With the service water pumphouse inoperable, restore the service water pumphouse to OPERABLE 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 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 />.

b. With the mechanical draft cooling tower inoperable, restore the cooling tower to OPERABLE 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 at least HOT STAND 8Y 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 tfe following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c. With the portable tower makeup pump system inoperable, continue operation and notify the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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.

• With the cooling tower in operation with valves aligned for tunnel heat treat-ment, the tower basin level shall be maintained at greater than or equal to .

40.55 feet. I l

l SEABROOK - UNIT 1 3/4 7-14 I

PLANT SYSTEMS ULTIMATE HEAT SINK SURVEILLANCE REQUIREMENTS 4.7.5 The ultimate heat sink shall be determined OPERA 8LE:

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

1) Verifying the water level in the service water pumphouse to be atorabove5'-0",(minus36'-0"MeanSeaLevel,)and

2) Verifying the water in the mechanical draft cooling tower basin to be greater than or equal to a level of 42.15 feet,

b. At least once per week by verifying that the water in the mechanical draft cooling tower basin to be at a bulk average temperature of less than or equal to 67.3*F.

c. At least once per 31 days by:

1) Starting from the control room each UHS cooling tower fan that is required to be OPERABLE and operating each of those fans for at least 15 minutes, and

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

d. At least once per 18 months by verifying automatic actuation of each cooling tower fan on a Tower Actuation test signal.

o SEABROOK - UNIT 1 3/4 7-15

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RADI0 ACTIVE EFFLUENTS 4

,' BASES 3/4.11.4 TOTAL DOSE (Continued)

THE PUBLIC from other uranius fuel cycle cesisnegligible,withtheexcepk tionthatdosecontributionsfromother/nuclearfuelcyclefacilitiesatthe i same site or within a radius of 8 km,must be considered. If the dose to any j i

MEMBEROFTHEPUBLICisestimatedtoexceedtherequirementsof40CFRPart190,}

the Special Report with a requestAor a variance (provided the release condi-

. tionsresultinginviolationof/0CFRPart190havenotalreadybeencorrected),;

in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is con- /

sidered to be a timely requist and fulfills the requirements of 40 CFR Part 190 /

until NRC staff action is completed. The variance only relates to the limits /

x of40CFRPart190,anddoesnotapplyinanywaytotheotherrequirementsforf dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and!

3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any /

period in which he/she is engaged in carrying out any operation that is part of the-nuclear fuel cycle.

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I SEABROOK - UNIT 1 8 3/4 11-6

l ADMINISTRATIVE CONTROLS l i

6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) ,

1 FUNCTION 6.2.3.1 The ISEG shall function to examine station operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of station design and operating experience information, including units of j similar design, which may indicate areas for improving station safety. The  ;

ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving station safety to the Executive Assistant to the Senior Vice President. j

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COMPOSITION 1 l

6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time l engineers located on site. Each shall have a bachelor's degree in engineering l or related science and at least 2 years professional level experience in his I field, at least 1 year of which experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of station activities to provide independent verification

• that these activities are performed correctly and that human errors are reduced as much as practical.

RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Executive Assistant to the Senior Vice President.

6.2.4 SHIFT TECHNICAL ADVISOR co mma nder

6. 2.4. lg(covtrol ros m Advisor shall provide advisory technical support The Shift Technical to the ...if t Cuptr'9t:ndent- in the areas of thermal hydraulics, reactor engi-neering, and plant analysis with regard to the safe operation of the station.

6.3 TRAINING 6.3.1 A retraining and replacement licensed training program for the station staff shall be maintained under the direction of the Training Center Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-197 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the NRC letter dated March 28, 1980 to all licensees, and shall include familiarization with relevant industry operational experience.

"Not responsible for sign-off function.

l SEABROOK - UNIT 1 6-5 l

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