ML20206H659

Forwards Revised Pages to Inservice Testing Program for Pumps & Valves (SER Outstanding Issue 4).Pages Reflect Changes to Test Requirements for Main Steam Sys Fuel Pool, Containment Purge Exhaust Sys & post-accident Sampling Sys

ML20206H659
Person / Time
Site:	Seabrook
Issue date:	06/23/1986
From:	George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Noonan V Office of Nuclear Reactor Regulation
References
SBN-1136, NUDOCS 8606260249
Download: ML20206H659 (16)

Text

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I George S. Thomas Vice President Nuclect Produc* ion Pubuc Service of New Hampshire New Hampshire Yankee Division SBN-ll36 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-915), dated December 31, 1985,

" Inservice Testing (IST) of Pumps and Valves (SER Outstanding Issue No. 4)", J. DeVincentis to V. S. Noonan (c) PSNH Letter (SBN-1086), dated June 4, 1986, " Inservice Testing (IST) of Pumps and Valves (SER Outstanding Issue No. 4)", G. S. Thomas to V. S. Noonan Subj ect:

Inservice Testing (IST) of Pumps and Valves (SER Outstanding Issue No. 4)

Dear Sir:

As a result of a phone conversation with Mr. Clair Ransom of EG&G in Idaho, several revisions have been made to the New Hampshire Yankee IST Program. The pages reflecting those changes are enclosed as follows:

Enclosure A - Figure 5.3, Valve Testing Requirements for the Main Steam System, P&ID 202074/202110.

Enclosure B - Figure 5.3, Valve Testing Requirements for the Fuel Pool and Containment Purge Exhaust System, P&ID 604131.

Enclosure C - Figure 5.3, Valve Testing Requirements for the Post Accident Sampling System, P&ID 804978.

Enclosure D - Figure 5.3, Valve Testing Requirements for the Reactor Coolant - Reactor Vessel System, P&ID 805002.

8606260249 860623 PDR ADOCK 0500 3

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Y P.O. Box 300 Seabrook, NH O3874. Telephone (603) 474-9521 1I

United States Nuclear Regulatory Commission June 23, 1986 Attention:

Mr. Vincent S. Noonan Page 2 Enclosure E - Figure 5.3, Valve Testing Requirements for the Reactor Coolant Drain Tank System, P&ID 805040.,

Enclosure F - Revised Figure 5.4 (Note 32 was deleted).

Enclosure G - Revised Figure 5.4 (Note 54 was deleted).

Enclosure H - Section 6.1 (V-8 deleted).

Enclosure I - Section t.1 (V-42 revised).

Enclosure J - Section 6.1 (V-43 deleted)'.

Enclosure K - Section 6.1 (V-46 added).

Enclosure L - Section 6.1 (V-47 added).

Enclosure M - Figure 5.3 Valve Testing Requirements for Residual Heat Removal System P&ID 805008.

Enclosure N - Figure 5.3 Valve Testing Requirements for Safety Injection High Head P&ID 805010.

We trust that this additional information is acceptable and request that it be reflected in the upcoming supplement to Seabrook SER.

Please contact Mr. James Connolly at (603) 474-9574, extension 3107, regarding any questions on this information.

Very truly yours, G or S. Thomas Enclosures cc: ASLB Service List em7Fv-r

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ENCLOSURE F TO SBN-1136 (continued)

VALVE TESTING REQUIREMENTS NOTES 27.

N/A l

28.

These valves cannot be exercised without the initiation of containment spray flow into the containment building quarterly during power operation or during cold shutdowns. These valves shall be partially disassembled, inspected, and manually exercised on a staggered sampling basis each refueling cutage. (Relief Request V-27.)

29.

This valve cannot be exercised by system flow without substantial amounts of water in the containment sumps being pumped by the spray and RHR pumps.

This valve will be exercised during refueling outages by disassembly and l

j mechanical exercise on a staggered sampling basis.

(Relief Request V-28.)

30.

This check valve is normally open during plant operation.

Its function is It is to prevent reverse flow, and shall be tested during cold shutdown.

impractical to shut down at three month intervals to perform a full closure test.

(Relief Request V-6.)

31.

Exercising this valve during power operations is impractical and would align the charging pump suctions of the RWST which could cause a sudden increase in the reactor coolant system boron inventory. This valve shall be full-stroke exercised during cold shutdowns. (Relief Request V-26.)

32.

N/A l

33.

N/A 34.

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35.

N/A 36.

It is impractical to full-stroke exercise these valves on a quarterly basis

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because these valves are not in the pump test flow path. These valves can-not be full-stroke exercised during cold shutdowns because there is no flow path back to the RWST.' Testing during cold shutdowns would require flow to be established into the RCS where there is no additional volume to add the additional inventory. These valves will be full stroke exercised l*

during refueling outages. (Relief Request V-31.)

(* - Relief Requests refer to relief requested in IST submittal to the NRC.)

Rev. 1 0

ENCLOSURE G TO SBN-1136 (continued)

49. These valves are not provided with power operators, therefore, the measuring of stroke time is not measured for these valves.

50. During quarterly pump testing of the EFW turbine pump, there is insufficient flow to full-stroke exercise these valves in accordance with the require-ments of the Code. These valves are partially stroked during the quarterly pump test. These valves shall be full-stroke exercised during plant cool-down to cold shutdown or heatup from cold shutdown when there is sufficient steam available to full-stroke exercise these valves.

(Relief Request V-41.) *

51. These valves shall additionally be tested to closed position because they are required to close in the event of a main steam line break.

52. These valves cannot be full-stroke exercised quarterly during power operation, or during cold shutdowns. These valves shall be partially disassembled, inspected and manually exercised on a staggered sampling basis each refueling.

(Relief Request V-42.)

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53. These valves shall be partially stroked during cold shutdowns.

54. N/A

55. It is impractical t'o measure the limiting value of full-stroke time of these valves. The safety function of these valves is to open to support the startup of its respective diesel to provide rated frequency and voltage in less than 10 seconds. Successful startup of each emergency diesel generator within the above specified conditions is dependent upon the proper operation and speed of these valves. Additional Code required full-stroke time measurement of these valves will not increase the assurance that the diesel generators will start as required.

Upon failure of the diesel generators to start as required, corrective action shall be taken to assure proper diesel startup conditions.

(Relief Request V-44.)

56. Exercising these valves at any periodic frequency is impractical. The primary function of these valves is to modulate to control the temperature and pres-sure of the cooling water of each emergency diesel generator. Code required full-stroke exercising of these valves would not verify the operability of these valves. Periodic operation of the diesels verifies operability of these valves. These valves are included in the inservice test program because of their fail-safe function. These valves shall be verified on a quarterly basis that they fail to maximum cooling position upon loss of actuator power.

(Relief Request V-45.)

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57. These valves shall additionally be full-stroke exercise tested open.

(* - Relief Requests refer to relief requested in IST submittal to the NRC. )

Rev. 1 I

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ENCLOSURE H TO SBN-1136 Relief Request:

V-8 (Deleted)

Valves:

Category:

Code Class:

Function:

Test Requirements:

Basis for Relief:

Alternate Testing:

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• Rev. 1

ENCLOSURE I TO SBN-1136 Relief Request:

V-42 Valves:

SI-VS, SI-V6, SI-V20, SI-V21, SI-V35, SI-V36, SI-V50 and SI-V51 Category:

AC Code Class:

1 Function:

(Active) Reactor Coolant Pressure Boundary Isolation Valves Test Requirements:

IWV-3520 (3 months)

Basis for Relief:

These valves cannot be full-stroke exercised quarterly during power operation because the safety injection accumu-lators have insufficient pressure to flow into the RCS.

Additionally, valves (SI-VS, SI-v20, SI-V35 and SI-V50) can-not be exercised quarterly during power operation because the RHR pumps have insufficient pressure to flow into the RCS.

During cold shutdowns, there is not sufficient flow using the RHR pumps to full-stroke exercise these valves (SI-V5, SI-V20, SI-V35 and SI-V50).

These valves shall be partially stroked during cold shutdowns.

Also, during cold shutdowns these valves cannot be exercised because the accumulator isolation valves (SI-V3, SI-V17, SI-V32 and SI-V47) are required by the plant technical speci-fications Section 4.5.2 to be closed with power removed from the operators.

SI flow from the accumulators could also risk low-temperature overpressurization of the RCS.

Alternate Testing: These valves are divided into two groups. One group con-sists of SI-V5, SI-V20, SI-V35 and SI-V50. The other group consists of SI-V6, SI-V21, SI-V36 and SI-V51.

One valve from each group shall be partially disassembled, inspected and manually exercised on a staggered sampling basis each refueling outage. At each disassembly, it shall be verified that the disassembled valve is capable of full stroking and that its internals are structurally sound (no loose or corroded parts).

In the event that the disassembled valve's full stroke capability is in question, all valves in this group be disassembled.

j Rev. 1

ENCLOSURE J TO SBN-1136 Relief Request:

V-43 (Deleted)

Valves:

Category:

Code Class:

Function:

Test Requirements:

Basis for Relief:

Alternate Testing:

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Rev. 1

l ENCLOSURE K TO SBN-1136 Relief Request:

V-46 Valves:

RH-V21 and RH-V22 i

Category:

B Code Class:

2 Function:

(Active) Residual Heat Removal System Crossover Valves Test Requirements:

IWV-3410 (3 months) j Basis for Relief:

Exercising these valves during power operations is imprac-tical.

Closing either valve would render the RHR system inoperable by isolating two of the four cold leg injection paths to the reactor coolant system from each RHR pump.

Seabrook Station Technical Specifications (3.5.2) require that there be at least one operable RHR pump for emergency core cooling during operational modes 1, 2 and 3.

Closing either of these valves could inhibit the ability of the RHR system to adequately respond to a large break loss-of-coolant accident.

Alternate Testing:

These valves shall be full stroke exercised during cold shutdowns.

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Rev. 1

ENCLOSURE L TO SBN-1136 Relief Request:

V-47 Valves:

SI-V93 Ca tegory :

B Code Class:

2 Function:

(Active) Minimum Flow Recirculation Isolation for SI-P-6A and SI-P-6B l

Test Requirements:

IW-3410 (3 months) i Basis for Relief:

Isolating this valve during power operations is imprac-tical.

Isolating this valve would render both safety injection pumps inoperable in the event of a safety injec-tion actuation. The valve is designed to provide a mini-mum flow through the safety injection pumps during the time of an event when the RCS pressure is greater than the shutoff head of the pumps.

Isolating this minimum flow path from both pumps would possibly damage the pumps and significantly affect the ability of these pumps to adequately perform their safety function.

Alternate Testing:

This valve shall be full stroke exercised during cold shutdowns.

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