ML20128A522

Amends 173 & 172 to Licenses DPR-32 & DPR-37,respectively, Revising TS to Modify Acceptance Criteria for Functional Testing of Anchor Darling Mechanical Snubbers

ML20128A522
Person / Time
Site:	Surry
Issue date:	01/22/1993
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20128A498	List: ML20128A495 ML20128A522 ML20128A558
References
NUDOCS 9302020237
Download: ML20128A522 (10)

Text

- _ _ _ - _ -

'o

[ s terg#'o

" UNITED STATES

!" ' 1. NUCLEAR REGULATORY COMMISSION

{ ,l wAsmNOTON, D. C. 20566

\...../

VIRGINIA ELECTRIC AND POWER COMPANY QQCEET NO. 50-280 1URRY POWER STAT!Q!{. UNIT NO. I 6!iUIDMENT TO FACIllTY OPERATING LICENE Amendment No. 173 License No. DPR-32

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Virginia Electric and Power Company (the licensee) dated Seatember 4, 1992, complies with the standards and requirements of tie Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, he provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9302020237 930122 DR ADDCK 0500 0 <

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of facility Operating License No. OPR-32 is hereby amended to read as follows:

(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 173, are hereby_ incor porated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION k '

H rbert N. Berkow, Director-t ,

Froject Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation ,

Attachment:

Changes to the Technical Specifications Date of issuance: January 22, 1993 '

l  :

- u __ _ _. _ ,_ _ _ .,_._ _ _ _ _.

s :sg,

/ 'o

',, UNITED sT ATES

['

g, g

t NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20555

%,...../

11RGIf11A ELECT.8JC AtiD POWER COMPANY DQCLET NO. 50-201 SURRY POWER STATION. UNIT l10. 2 AMENDMENT TO FAClllTY OPERATING LICENS.f.

Amenarnent No.172 License No. DPR-37

1. The Nucicar Regulatory Commission (the Commission) has found that:

A. The application for amendment by Virginia Electric and Power Company (the licensee) dated Sc)tember 4,1992, complies with the standards and requirements of tie Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in cor.formity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of t.he public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

9. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the-public; and E. The issuance of this amendment is in accordance with 10 CFR Part M of the Commission's regulations and all applicable requirements have been satisfied.

l

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of facility Operating License No. OPR-37 is hereby amended to read as follows:

(B) Technical,$pecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 172 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR Tile NUCLEAR REGULATORY COMMISSION C

<He ertN.Berkow,1Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: January 22, 1993

'4 .

5 y

?

6JTJf_CHMENT TO LICENSE AMENDMENT ABENDMENTNO.173 TO FACIllTY OPERATING tlCENSE NO. OPR-32 AMENDMENT NO. 172 TO FACIllTY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 '

Reviso Appendix A as follows:

Remove P3aes Insert Paoes TS 4.17-1 TS 4.17-1 TS 4.17-3 TS 4;,17-3 TS 4.17-4 15 4.17-4 TS 4.17-5 TS 4.17-5 TS 4.17-8 TS 4.17-8 P

e - w r - w- w -- r.- e r, w - ,---y-

_ . _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - _ _ _ _ _ _ _ _ _ ~ _.-

l TS 4.171 4.17 SHOCK SUPPRESSORS (SNUBBERS)

Acolicabilliv Applies to all hydraulic and mechanical shock suppressors (snubbers) which are required to protect the Reactor Coolant System and other safety related systems. Snubbers excluded from this inspection are those installed on non-safety related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety related system.

O.bj2rdlY2 To specify the minimum frequency and type of surveillance to be applied to the hydraulic and mechanical snubbers required to protect the Reactor Coolant System and other safety related systems.

Soecification Each snubber shall be demonstrated OPERABLE by performing the following  ;

augmented inservice inspection program and the requirements of Specification 4.0.3. As used in this specification, " type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.

A. Visual Insoections

1. Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be Inspected independently according to the schedule determined by Table 4.171. The visualinspection interval of each category of snubber shall be determined based upon the criteria provided in Table 4.171.

Amendment Nos. 173 and 172

. . .. - _ ... _ _. _ . _ --- _ _ . . _ ~ - -- - _. _ _ . _ . _ - . _ . . , . _ . _

i TS 4.17 3

4. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the action requirements of Specification 3.20 shall be met.

C, Functional Tests

1. At least once per 18 months during shutdown, a representative sample of 10% of the total of each type of snubber used in the plant shall be functionally tested using either an in place test machine or a bench test.

2. The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. This representative sample shall not, to the extent practicable, include those snubbers .

tested in a previous representative sample,

3. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:

a. the first snubber away from each reactor vessel nozzle, b, snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc), and

c. snubbers within 10 feet of the discharge from a safety relief valve.

Amendment Nos. 173 and 172

TS 4.17 4

4. Snubbers identified as "Especially Difficult to Remove" or in "High Radiation Zone During Shutdown" shall also be included in the representative sample.'

5. In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spara snubber has been installed in place of a failed snubber, then both the failed snubber (if it is reoaired and installed in another position) and the spare snubber shall be ratested Test results of these snubbers may not be included for the resampling.

6. For each snubber that does not meet the functional acceptance criteria of Specification 4.17.D or 4.17.E, an additional 10% of that type of snubber shall be functionally tested,

7. For snubbers of 50 kips and above that are extremely difficult to remove or in high radiation zones that fall the functional testing, an engineering evaluation is required to determine the failure mode.

If the failure is determined to be non generic, an additional 10% of that type will be tested during the next functional test period.

8. If any snubber selected for functional testing either falls to lockup or falls to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

Permanent or other exemptions from functional testing for individual snubbers in l

these categories may be granted by the Commission only if a justifiable basis for l exemption is presented and/or snubber life destructive testing was performed to i qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

Amendment O s, 173 and 172-

TS 4.17 5  :

9. For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

D. Hvdraulic Snubbers Functional Test Acceotance Criteria

1. The hydraulic snubbor functional test sha!! verify that;

a. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

b. Snubber bleed, or release rate, where required, is within the specified range in compression and tension. For ,

snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified, f

E. Mechanical Snubbers Functional Test Acceotance Criteria i 1. The mschanical snubbers functional test shall verify that:

a. The drag force of the snubber in both tension and

! compression is less than the specified maximum drag force.

l l b. Activation (restraining ' action) is achieved within the specified range of velocity 'n both tension and compression.

Amendment Hos,173 and 172

TS 4.17 8 To provide assurance of snubber functional reliability, a representative samplo of the installed snubbers will be functionally tested during plant shutdowns at 18 month intel /als. Functional testing is to be in accordance with the ASME Section XI Inservice inspection program approved by the NRC. Observed failures of these sample snubbers shall require functional testing of additional units.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spri.ig replaced, in high radiation area, in high temperature area, etc....). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These rocords will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not interaded to affect plant operatinn.

Amendment Hos. U3 and 172 1

__ _____ _ _ __ _____ _______